CN113488205B - Non-uniform tubular MA transmutation rod with function of flattening axial power of reactor core - Google Patents

Non-uniform tubular MA transmutation rod with function of flattening axial power of reactor core Download PDF

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CN113488205B
CN113488205B CN202110852206.7A CN202110852206A CN113488205B CN 113488205 B CN113488205 B CN 113488205B CN 202110852206 A CN202110852206 A CN 202110852206A CN 113488205 B CN113488205 B CN 113488205B
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lid
transmutation
mixed fuel
rod
section
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CN113488205A (en
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叶滨
张二品
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Southwest University of Science and Technology
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Southwest University of Science and Technology
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
    • G21C5/20—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a heterogeneous tubular MA transmutation rod with a flattening reactor core axial power function, which comprises the following components: a central layer positioned at the center of the heterogeneous tubular MA transmutation rod, the outside of the central layer is provided with 6 LiD/MA/UO 2 A layer of mixed fuel material is provided, 6 LiD/MA/UO 2 an air gap layer is arranged outside the mixed fuel layer, and a zirconium alloy cladding is arranged outside the air gap layer; the non-uniform tubular MA transmutation rod is axially provided with odd sections 6 LiD/MA/UO 2 A mixed fuel layer from the upper end of the heterogeneous tubular MA transmutation rod to the middle position, and each section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is gradually increased; from the middle position to the lower end of the non-uniform tubular MA transmutation rod, each section 6 LiD/MA/UO 2 The MA species fraction ratio in the mixed fuel layer decreases segment by segment. The non-uniform tubular MA transmutation rod provided by the invention improves the transmutation rate of MA nuclides, has a flattening effect on radial and axial power of a reactor core, can improve the conditions of overhigh neutron flux and low external flux in the reactor core, and reduces the power peak factors of all components in the reactor core.

Description

Non-uniform tubular MA transmutation rod with function of flattening axial power of reactor core
Technical Field
The invention belongs to the technical field of pressurized water reactor nuclear fuel transmutation assemblies, and particularly relates to a non-uniform tubular MA transmutation rod with a flattened reactor core axial power function.
Background
There are many sources of nuclear waste, and the vast majority of spent fuel produced by reactor operation. The radioactive waste is divided into low, medium and high radioactive waste according to the radioactivity level and short, medium and long radioactive waste according to the half-life period. Among the most interesting and urgent problems are how to dispose of a large amount of high level waste generated in a nuclear power plant, particularly Long-life high level waste (Long-lived High Level Wastes, LHLW for short).
The Long-life high level waste comprises Minor Actinides (MA) and Long-life fission products (Long-life Fiss)ion Products, LLFP for short). MA nuclides in spent fuel, mainly 237 Np、 241 Am、 243 Am、 244 Cm、 245 Cm, long-life nuclides. Although in small amounts, has strong radioactivity and long half-life, e.g 237 Np has a half-life of up to two hundred thousand years. At present, the scheme of long-term low-quality storage after solidification is often adopted for the treatment of spent fuel in China, but for long-life high-radioactivity nuclides such as MA, the situation that the underground water system is leaked into the biosphere to pollute due to geological activity and the like in the long-term sealing and storing process is difficult to ensure after the geology is deeply buried.
The technology of separation transmutation (Partitioning and Transmutation, abbreviated as P & T) is proposed in the great background of: the long-life actinides and long-life fission products are separated from the high-level waste, and then concentrated and put into a reactor for transmutation, so that the actinides and the fission products become stable or short-life nuclides.
Transmutation is the only method capable of converting long-life nuclides into short-life nuclides or stable nuclides, and a plurality of devices capable of being used for transmutation are provided, compared with fast reactor and ADS (accelerator driven subcritical system) transmutation devices, thermal reactors, particularly pressurized water reactors, are the most numerous reactor types of global commercial nuclear power plants, and are ideal reactor types for MA transmutation at present.
Related studies on thermal reactor transmutation have been conducted in france, japan, the united states, etc., in japan, pressurized water reactor transmutation has been conducted in depth, such as Tomohiko, etc., to study the neutron economy of MA transmutation in thermal reactors, and studies have shown that better neutron economy can be achieved when neutron flux is higher, while the Kunieda et al of the japanese patent also published a new nuclear database for long-life fission product transmutation studies in 2018.
There are also many domestic transmutation studies on MA in thermal reactors, such as using burnup procedures to study transmutation MA species in high flux thermal and pressurized water reactors, and related research schemes are proposed, including mixing MA with fuel, and making MA into individual transmutation rods to replace part of the fuel rods of the core. In addition, north China electricityUniversities and the like have also conducted related studies on minor actinide transmutation in burnable poison assemblies, and on the effect of MA transmutation on core safety in pressurized water reactors. These studies mainly show the effect of transmutation performance of transmutation by using pressurized water reactor and the effect of adding MA nuclides in pressurized water reactor on core parameters and performance, such as core K eff Neutron spectrum, neutron flux, etc.
237 Np、 241 Am、 243 Am、 244 The fission cross-section of these four MA species is in the high energy region (E>1 MeV) is higher and is associated with 235 U has a fission cross section equivalent to that of the energy region, but is very small in the low energy region, and is equivalent to 235 The fissile section of U in the low energy region is more than two orders of magnitude lower, so MA nuclides are directly loaded into the pressurized water reactor, and the direct fission rate is lower.
Meanwhile, the neutron spectrum characteristic of the thermopile is easy to cause the capture reaction of MA nuclides, so if a material can be added while loading MA transmutation materials to improve the neutron energy for transmutation, the direct fission rate of MA nuclides can be improved. There is thus a need for a transmutation rod structure that can increase the neutron energy of transmutation in the core, and thus the direct rate of fission of MA species.
Disclosure of Invention
It is an object of the present invention to address at least the above problems and/or disadvantages and to provide at least the advantages described below.
To achieve these objects and other advantages and in accordance with the purpose of the invention, there is provided a non-uniform tubular MA transmutation rod having a function of flattening axial power of a core, comprising:
a central layer positioned at the center of the heterogeneous tubular MA transmutation rod, the outside of the central layer is provided with 6 LiD/MA/UO 2 A mixed fuel layer, said 6 LiD/MA/UO 2 An air gap layer is arranged outside the mixed fuel layer, and a zirconium alloy cladding is arranged outside the air gap layer;
the non-uniform tubular MA transmutation rod is axially provided with odd sections 6 LiD/MA/UO 2 A mixed fuel layer, and two adjacent sections 6 LiD/MA/UO 2 The mass share of MA nuclides in the mixed fuel layers is different, and each section is from the upper end of the heterogeneous tubular MA transmutation rod to the middle position 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is gradually increased; from the middle position to the lower end of the non-uniform tubular MA transmutation rod, each section 6 LiD/MA/UO 2 The MA species fraction ratio in the mixed fuel layer decreases segment by segment.
Preferably, the central layer is a solid structure or a hollow void structure.
Preferably, the heterogeneous tubular MA transmutation rod is axially provided with three sections 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 Mixed fuel layer, second section 6 LiD/MA/UO 2 Mixed fuel bed and third section 6 LiD/MA/UO 2 A mixed fuel layer, wherein the first section 6 LiD/MA/UO 2 Mixed fuel bed and third section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 1-3%, and the second section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 5 percent, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
Preferably, the heterogeneous tubular MA transmutation rod is axially provided with five sections 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 Mixed fuel layer, second section 6 LiD/MA/UO 2 Mixed fuel layer, third section 6 LiD/MA/UO 2 Mixed fuel layer, fourth section 6 LiD/MA/UO 2 Mixed fuel bed and fifth section 6 LiD/MA/UO 2 A mixed fuel layer, wherein the first section 6 LiD/MA/UO 2 Mixed fuel bed and fifth section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 1 percent, and the second section 6 LiD/MA/UO 2 Mixed fuel layer and fourth stage 6 LiD/MA/UO 2 The proportion of MA nuclide in the mixed fuel layer is 3%Third section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 5 percent, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
Preferably, the heterogeneous tubular MA transmutation rod is provided with seven sections in the axial direction 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 Mixed fuel layer, second section 6 LiD/MA/UO 2 Mixed fuel layer, third section 6 LiD/MA/UO 2 Mixed fuel layer, fourth section 6 LiD/MA/UO 2 Mixed fuel layer, fifth section 6 LiD/MA/UO 2 Mixed fuel layer, sixth section 6 LiD/MA/UO 2 Mixed fuel layer and seventh section 6 LiD/MA/UO 2 A mixed fuel layer, wherein the first section 6 LiD/MA/UO 2 Mixed fuel layer and seventh section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 0 percent, and the second section 6 LiD/MA/UO 2 Mixed fuel layer and sixth section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 1 percent, and the third section 6 LiD/MA/UO 2 Mixed fuel bed and fifth section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 3%, and the fourth section is that 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 5 percent, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
Preferably, wherein the 6 LiD/MA/UO 2 The composition of MA nuclides in the mixed fuel layer comprises 237 Np、 241 Am、 243 Am, and 244 cm, where 237 The mass ratio of Np is 56.36%, 241 am is 26.48% by mass, 243 am is 12.03% by mass, 244 the mass ratio of Cm is 5.12%.
Preferably, the center positions of the fuel assembly in the x-axis direction and the y-axis direction are respectively provided with 2 non-uniform tubular MA transmutation rods, and the four corners of the fuel assembly are respectively provided with 3 non-uniform tubular MA transmutation rods, namely 16 non-uniform tubular MA transmutation rods are respectively provided in one fuel assembly; 36 groups of fuel assemblies with 3.1% fuel enrichment degree are loaded near the central position in the reactor core, and 60 groups of fuel assemblies with 3.1% fuel enrichment degree except the central position are loaded, namely 1536 heterogeneous tube type MA transmutation rods are loaded in one reactor core.
Preferably, the thickness of the tube wall of the heterogeneous tube type MA transmutation rod is 0.05 cm-0.3 cm.
The invention at least comprises the following beneficial effects:
the non-uniform tubular MA transmutation rod provided by the invention improves the transmutation rate of MA nuclides, and simultaneously the radial and axial power of the reactor core has a flattening effect;
after the heterogeneous tubular MA transmutation rods are reloaded into the reactor core, the conditions of high neutron flux in the reactor core and low neutron flux outside the reactor core can be improved, and the power peak factors of all components of the reactor core are reduced; in addition, MA nuclides can play a role of combustible poison in the reactor core, provide certain negative reactivity in the early operation stage of the reactor, and compensate certain positive reactivity in the later operation stage;
the MA transmutation rod is designed uniformly in an axial direction, so that not only the MA nuclide transmutation rate is improved, but also the radial power and the axial power of the reactor core can be effectively flattened, for example, a transmutation rod axial power scheme III is adopted, namely, the mass proportions of MA nuclides from two ends to the center are respectively 1%, 3% and 5%, and the mass proportions are as follows 6 LiD: MA=1:9 ratio addition 6 LiD, the pipe wall thickness is set to be 0.1cm, so that the axial power peak factor of the reactor core is improved to be 1.249 when the MA transmutation rods are not loaded, and the power peak shape is obviously improved.
Additional advantages, objects, and features of the invention will be set forth in part in the description which follows and in part will become apparent to those having ordinary skill in the art upon examination of the following or may be learned from practice of the invention.
Drawings
FIG. 1 is a schematic diagram of a non-uniform tubular MA transmutation rod with flattened core axial power functionality provided by the invention;
FIG. 2 is a schematic structural diagram of a non-uniform tubular MA transmutation rod of example 1;
FIG. 3 is a schematic structural diagram of a non-uniform tubular MA transmutation rod of example 2;
FIG. 4 is a schematic structural diagram of a non-uniform tubular MA transmutation rod of example 3;
FIG. 5 is a schematic structural diagram of a non-uniform tubular MA transmutation rod of example 4;
FIG. 6 is a schematic structural diagram of a uniform tubular MA transmutation rod of example 17;
FIG. 7 is a schematic illustration of the arrangement of non-uniform tubular MA transmutation rods in a fuel assembly;
FIG. 8 is a schematic illustration of the placement of fuel assemblies with non-uniform tubular MA transmutation rods in a core;
FIG. 9 is a comparison of the effect of various transmutation scenarios on the effective increment coefficient of the core over the lifetime;
FIG. 10 is a radial neutron flux distribution curve of a clean core without loaded uniform tubular MA transmutation rods;
FIG. 11 is a radial neutron flux distribution curve of a post-core loaded with uniform tubular MA transmutation rods;
FIG. 12 is a 1/4 core assembly thermoelectric factor after loading of uniform tubular MA transmutation rods;
FIG. 13 is a 1/4 core assembly thermoelectric factor after further optimization;
FIG. 14 is a core axial power distribution under different scenarios;
FIG. 15 is a diagram of 237 A change curve of Np nuclear density with burn-up time;
FIG. 16 is a diagram of 241 A variation of Am nuclear density with burn time;
FIG. 17 is a diagram of 243 A variation of Am nuclear density with burn time;
FIG. 18 is a diagram of 244 A variation curve of Cm nuclear density with burn time;
FIG. 19 is a plot of MA nuclide density versus burnup time;
FIG. 20 is a graph showing wall thickness versus hollow transmutation tubing 237 An influence curve of Np transmutation rate;
FIG. 21 is a hollow transmutationWall thickness pair of variable tube 241 An influence curve of Am transmutation rate;
FIG. 22 is a graph showing wall thickness versus hollow transmutation tubing 243 An influence curve of Am transmutation rate;
FIG. 23 is a drawing of a hollow transmutation tube having a wall thickness of 244 An influence curve of Cm transmutation rate;
fig. 24 is a graph showing the effect of wall thickness of a hollow transmutation tube on total transmutation rate of MA species.
Detailed Description
The present invention is described in further detail below with reference to the drawings to enable those skilled in the art to practice the invention by referring to the description.
It will be understood that terms, such as "having," "including," and "comprising," as used herein, do not preclude the presence or addition of one or more other elements or groups thereof.
Example 1
As shown in fig. 1 and 2: the non-uniform tube type MA transmutation rod with the function of flattening the axial power of the reactor core provided by the embodiment comprises the following structures:
a central layer 1 positioned at the center of the heterogeneous tubular MA transmutation rod, wherein the outside of the central layer 1 is provided with 6 LiD/MA/UO 2 The thickness of the tube wall of the heterogeneous tube type MA transmutation rod is 0.1cm, which is a mixed fuel layer 2 6 LiD/MA/UO 2 An air gap layer 3 is arranged outside the mixed fuel layer 2, and a zirconium alloy cladding 4 is arranged outside the air gap layer 3;
three sections are arranged on the non-uniform tubular MA transmutation rod in the axial direction 6 LiD/MA/UO 2 A mixed fuel layer, and two adjacent sections 6 LiD/MA/UO 2 The mass share of MA nuclides in the mixed fuel layers is different, and each section is from the upper end of the heterogeneous tubular MA transmutation rod to the middle position 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is gradually increased; from the middle position to the lower end of the non-uniform tubular MA transmutation rod, each section 6 LiD/MA/UO 2 The MA species fraction ratio in the mixed fuel layer decreases segment by segment. Sequentially marking the first section from the upper end to the lower end of the non-uniform tube type MA transmutation rod 6 LiD/MA/UO 2 A mixed fuel layer 21, a second section 6 LiD/MA/UO 2 Mixing fuel layer 22 and third section 6 LiD/MA/UO 2 A mixed fuel layer 23, in which the first stage 6 LiD/MA/UO 2 Mixed fuel layer 21 and third section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer 23 is 1%, and the second section 6 LiD/MA/UO 2 The proportion of MA species in the mixed fuel layer 22 is 5%, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
Example 2
As shown in fig. 1 and 3, the heterogeneous tubular MA transmutation rod with the function of flattening the axial power of the reactor core of the present embodiment has a structure including:
a central layer 1 positioned at the center of the heterogeneous tubular MA transmutation rod, wherein the outside of the central layer 1 is provided with 6 LiD/MA/UO 2 The thickness of the tube wall of the heterogeneous tube type MA transmutation rod is 0.1cm, which is a mixed fuel layer 1 6 LiD/MA/UO 2 An air gap layer 3 is arranged outside the mixed fuel layer 2, and a zirconium alloy cladding 4 is arranged outside the air gap layer 3;
the non-uniform tubular MA transmutation rod is axially provided with three sections 6 LiD/MA/UO 2 Mixing fuel layers, and two adjacent sections 6 LiD/MA/UO 2 The mass share of MA nuclides in the mixed fuel layers is different, and each section is from the upper end of the heterogeneous tubular MA transmutation rod to the middle position 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is gradually increased; from the middle position to the lower end of the non-uniform tubular MA transmutation rod, each section 6 LiD/MA/UO 2 The MA species fraction ratio in the mixed fuel layer decreases segment by segment. Sequentially marking the first section from the upper end to the lower end of the non-uniform tube type MA transmutation rod 6 LiD/MA/UO 2 Mixed fuel layer 24, second section 6 LiD/MA/UO 2 Mixed fuel layer 25 and third section 6 LiD/MA/UO 2 A mixed fuel layer 26, in which the first section 6 LiD/MA/UO 2 Mixing fuel layer 24 and third section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer 26 is 3%, the second stage 6 LiD/MA/UO 2 The proportion of MA species in the mixed fuel layer 25 is 5%, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
Example 3
As shown in fig. 1 and 4, the heterogeneous tubular MA transmutation rod with flattened core axial power function of the present embodiment includes:
a central layer 1 positioned at the center of the heterogeneous tubular MA transmutation rod, wherein the outside of the central layer 1 is provided with 6 LiD/MA/UO 2 The thickness of the tube wall of the heterogeneous tube type MA transmutation rod is 0.1cm, which is a mixed fuel layer 2 6 LiD/MA/UO 2 An air gap layer 3 is arranged outside the mixed fuel layer 2, and a zirconium alloy cladding 4 is arranged outside the air gap layer 3;
the heterogeneous tubular MA transmutation rod is axially provided with five sections 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 A mixed fuel layer 27, a second section 6 LiD/MA/UO 2 Mixed fuel layer 28, third section 6 LiD/MA/UO 2 Mixed fuel layer 29, fourth stage 6 LiD/MA/UO 2 Mixing fuel layer 210 and fifth section 6 LiD/MA/UO 2 A mixed fuel layer 211, wherein the first section 6 LiD/MA/UO 2 Mixing fuel layer 27 and fifth stage 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer 211 is 1%, the second section 6 LiD/MA/UO 2 Mixing fuel layer 28 and fourth stage 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer 210 is 3%, and the third section is 6 LiD/MA/UO 2 The portion of MA species in the mixed fuel layer 29 is 5%, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
Example 4
As shown in fig. 1 and 5, the heterogeneous tube type MA transmutation rod with the function of flattening the axial power of the reactor core of the present embodiment has a structure including:
a central layer 1 positioned at the center of the heterogeneous tubular MA transmutation rod, wherein the outside of the central layer 1 is provided with 6 LiD/MA/UO 2 The thickness of the tube wall of the heterogeneous tube type MA transmutation rod is 0.1cm, which is a mixed fuel layer 2 6 LiD/MA/UO 2 An air gap layer 3 is arranged outside the mixed fuel layer 2, and a zirconium alloy cladding 4 is arranged outside the air gap layer 3;
the heterogeneous tubular MA transmutation rod is axially provided with seven sections 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 The mixed fuel layer 212, second section 6 LiD/MA/UO 2 Mixed fuel layer 213, third section 6 LiD/MA/UO 2 Mixed fuel layer 214, fourth stage 6 LiD/MA/UO 2 Mixed fuel layer 215, fifth stage 6 LiD/MA/UO 2 Mixed fuel layer 216, sixth stage 6 LiD/MA/UO 2 Mixed fuel layer 217 and seventh stage 6 LiD/MA/UO 2 A mixed fuel layer 218, wherein the first section 6 LiD/MA/UO 2 Mixing fuel layer 212 and seventh section 6 LiD/MA/UO 2 The MA species fraction in the mixed fuel layer 218 is 0%, the second stage 6 LiD/MA/UO 2 Mixed fuel layer 213 and sixth section 6 LiD/MA/UO 2 The MA nuclide fraction in the mixed fuel layer 217 is 1%, the third stage 6 LiD/MA/UO 2 Mixing fuel layer 214 and fifth section 6 LiD/MA/UO 2 The MA nuclide fraction in the mixed fuel layer 216 is 3%, the fourth segment is 6 LiD/MA/UO 2 The MA species fraction in the mixed fuel layer 215 is 5%, 6 the mass ratio of LiD to MA nucleolin is fixed at 1:9.
Example 5
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 1, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.05cm.
Example 6
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 1, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.15cm.
Example 7
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 1, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.2cm.
Example 8
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 2, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.05cm.
Example 9
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 2, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.15cm.
Example 10
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 2, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.2cm.
Example 11
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 3, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.05cm.
Example 12
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core of the embodiment has the same structure as the non-uniform tubular MA transmutation rod of embodiment 3, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.15cm.
Example 13
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 3, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.2cm.
Example 14
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 4, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.05cm.
Example 15
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core of the embodiment has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 4, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.15cm.
Example 16
The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core has the same structure as the non-uniform tubular MA transmutation rod of the embodiment 4, but the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.2cm.
Example 17
As shown in fig. 6, the structure of the uniform tubular MA transmutation rod provided in this embodiment includes:
a central layer 5 positioned at the center of the uniform tubular MA transmutation rod, the outside of the central layer 5 is provided with 6 LiD/MA/UO 2 The fuel mixture layer 6 is mixed with a fuel, 6 LiD/MA/UO 2 the mixed fuel layers 6 are uniformly distributed in the axial direction of the uniform tubular MA transmutation rod, the 6 LiD/MA/UO 2 An air gap layer 7 is arranged outside the mixed fuel layer 6, and a zirconium alloy cladding 8 is arranged outside the air gap layer 7; the tube wall thickness of the uniform tube MA transmutation rod was 0.05cm.
Example 18
The uniform tubular MA transmutation rod of this example has the same structure as the uniform tubular MA transmutation rod of example 17, but the thickness of the tube wall of the uniform tubular MA transmutation rod is 0.1cm.
Example 19
The uniform tubular MA transmutation rod of this example has the same structure as the uniform tubular MA transmutation rod of example 17, but the thickness of the tube wall of the uniform tubular MA transmutation rod is 0.15cm.
Example 20
The uniform tubular MA transmutation rod of this example has the same structure as the uniform tubular MA transmutation rod of example 17, but the thickness of the tube wall of the uniform tubular MA transmutation rod is 0.2cm.
Example 21
The uniform tubular MA transmutation rod of this example has the same structure as the uniform tubular MA transmutation rod of example 17, but the thickness of the tube wall of the uniform tubular MA transmutation rod is 0.25cm.
Example 22
The uniform tubular MA transmutation rod of this example has the same structure as the uniform tubular MA transmutation rod of example 17, but the thickness of the tube wall of the uniform tubular MA transmutation rod is 0.3cm.
Examples 1, 2, 3 and 4 are four different designs of non-uniform tubular MA transmutation bars with flattened core axial power of the present invention, respectively, examples 5-7 are the same designs as example 1, but 6 LiD/MA/UO 2 The thickness of the mixed fuel layers is different; examples 8 to 10 are the same in structure as example 2, but 6 LiD/MA/UO 2 The thicknesses of the mixed fuel layers are different; examples 11 to 13 are the same design as example 3, but 6 LiD/MA/UO 2 The thickness of the mixed fuel layers is different; examples 14 to 16 are the same design as example 4, but 6 LiD/MA/UO 2 The thickness of the mixed fuel layers is different; examples 17 to 22 are designs of a uniform tubular MA transmutation rod, wherein each example 6 LiD/MA/UO 2 The thickness of the mixed fuel layers is different. Examples 1, 5, 6 and 7 are referred to as scheme one, examples 2, 8, 9 and 10 are referred to as scheme two, examples 3, 11, 12 and 13 are referred to as scheme three, and examples 4, 14, 15 and 16 are referred to as scheme four.
By loading examples 17-22 into the core, the effect of uniform tubular MA transmutation rods on core performance parameters was investigated. MA nuclides are respectively adjusted in MA/UO based on the embodiment 17 to the embodiment 22 2 Mass fraction and mass fraction in a mixed material 6 The proportion of LiD and MA nuclides is further studied 2 The effect on the transmutation properties of the film, 6 influence of ratio of LiD to MA on transmutation performance; MA/UO 2 The mass fractions of MA in the mixture are respectively 1%, 3% and 5%, 6 LiD to MA ratios were studied in the range of 1:9, 2:8, 3:7, 4:6 and 5:5.
The uniform tubular MA transmutation rods or uniform tubular MA transmutation rods of each of the above embodiments are loaded into a fuel assembly, and then the fuel assembly is loaded into the core. The loading schemes of the uniform tubular MA transmutation rods and the non-uniform tubular MA transmutation rods in the fuel assembly as shown in fig. 7, wherein 2 transmutation rods 9 are respectively loaded in the x-axis direction and the y-axis direction of the center of the fuel assembly 10, 3 transmutation rods 9 are respectively loaded in the 4 corners of the fuel assembly 10, namely 16 transmutation rods 9 are loaded in total in one fuel assembly 10; the loading schematic of the fuel assemblies 10 with transmutation rods 9 in the core 11 as shown in fig. 8 is that 36 groups of assemblies 10 with 3.1% fuel enrichment and 60 groups of assemblies 10 with 3.1% fuel enrichment except the center are loaded in the whole core 11, and 1536 transmutation rods 9 are loaded in total in one core.
The addition of MA to a reactor obviously results in a change in core performance parameters, so that the effect of loading transmutation rods on core performance parameters needs to be considered while transmutation performance studies are being conducted. The k of each scheme is counted by critical calculation, burnup calculation and using a counter by using an RMC program eff And energy spectrum, etc., the effect of each scheme on core performance parameters is analyzed.
According to clean reactor core, loading MA transmutation rods (none 6 LiD, loading and adding 6 The research ideas of the transmutation rods of LiD and the axially non-uniform tubular MA transmutation rods are that four groups of burnup calculation data of a more typical scheme are selected to obtain a curve of the change of the effective increment coefficient of the reactor core along with the burnup time step of 540 days, as shown in figure 9.
From FIG. 9, it can be seen that after loading the MA transmutation rods, the initial k of the core eff Decrease, but in the subsequent burnup time step, k eff Almost unchanged, since MA species can act as a burnable poison rod, in generalTo be specific, the reactor core k with a proper amount of burnable poison is added eff The effective increment coefficient of the reactor core is gradually increased along with the progress of the burnup, because a large amount of burnup poison introduces larger negative reactivity in the initial burnup period to lead the reactor core k eff A significant drop occurs as the core operates, the burnable poison gradually decreases, the negative reactivity introduced also gradually decreases, and fissionable nuclides may also be generated, thereby gradually returning the core reactivity.
Where k is eff The reason for the unchanged is that the mass ratio of the MA nuclides in the transmutation rod is only 5 percent, the MA nuclides have the fissile performance, the loading of the transmutation rod also means the addition of fissionable fuel, so the reduction of the effective increment coefficient in the early stage is less, and the fission of the MA nuclides in the later stage plays the role of the burnable poison to lead k eff And remains stable.
Different proportions of the initial reactor (without MA) energy spectrum and the transmutation rod with the loading MA mass share of 5 percent are added into the transmutation rod 6 LiD and other schemes and axial non-uniform schemes. Transmutation material is 6 LiD/MA/UO 2 The transmutation rods of the mixed materials have less effect on the energy spectrum of the core. But in the thermal energy zone, follow 6 And the neutron flux is improved by increasing the ratio of LiD to MA. Calculation and research show that in transmutation rod 6 An increase in the LiD loading will cause a transmutation rod to be internally filled with 235 The U disappearance rate is reduced (difference between initial nuclear density and final nuclear density of burnup) so that the thermal neutron absorber has larger absorption cross section 235 Absorption of U is reduced, and 6 LiD as thermal fast neutron conversion material to enable MA nuclide 238 The fission reaction of U is increased, so that the neutron flux in the high-energy region is almost unchanged, and the neutrons in the heat energy region follow up 6 The LiD loading increases and improves.
As shown in fig. 10 and 11, the radial relative neutron flux change of the reactor core of the initial reactor and the reactor core loaded with the uniform tube type MA transmutation rods is reflected, and as can be seen from the graph, in the initial reactor, the radial neutron flux of the reactor core is generally high and low on both sides, but has the phenomenon of 'high-low staggering', and the position with low thermal neutron flux corresponds to the position with high-energy neutrons, because the enrichment degree of the fuel in the fuel assembly in the middle area is respectively 3.1 percent and 2.4 percent on the radial section, when the enrichment degree of the fuel is 3.1 percent, the absorption capacity of the fuel assembly for thermal neutrons is stronger, and meanwhile, the high-energy neutrons released by fission are more. In addition, it can be seen that in the curve with E <1eV, the neutron flux on the left and right sides is higher, because the pressurized water reactor has light water as a reflecting layer, and the neutron fluence rate distribution of the core flux at the outer edge of the core is improved due to the reflecting effect of the reflecting layer. And because the fuel enrichment degree of the fuel assemblies at the outermost periphery of the reactor core is 4.4%, the assemblies have strong absorption capacity for thermal neutrons, so that the neutron flux at the corresponding position in the curve is lower than the flux in the reflecting layer.
After the reactor core of the reactor core fuel assembly is loaded with MA transmutation rods, the flux of the high-medium low energy region of the reactor core is in a concave shape, and the flux of the corresponding region is reduced due to the fact that the MA transmutation rods loaded in the inner region of the reactor core are more and the MA nuclides absorb a large amount of neutrons with high-medium low energy. No transmutation rods are placed in the central fuel assembly so that the thermal neutron flux has a small peak in the center.
Since the power of the core is proportional to neutron flux, the trend of variation of the power distribution non-uniformity coefficient of the assemblies in the central region relative to the core after loading the MA transmutation rods is the same as the trend of variation of neutron flux, and the fuel enrichment degree in the two assemblies at the upper right corner is higher (4.4%), so that the power distribution non-uniformity coefficient of the assemblies is rather higher, although the transmutation rod loading scheme in the scheme does not have a great advantage in flattening radial power, the idea of flattening radial power of the core is provided, namely, the power distribution non-uniformity coefficient of the assemblies relative to the core can be reduced by loading the transmutation rods in the assemblies with higher fuel enrichment degree or higher individual power distribution non-uniformity coefficient. According to the idea, a transmutation rod loading scheme is further improved, MA transmutation rods are loaded into fuel assemblies with enrichment degree of 3.1% and assemblies with enrichment degree of 4.4% in a reactor core region, 60+8 fuel assemblies are used, and a reactor core power distribution non-uniformity coefficient shown in fig. 13 can be obtained. The power non-uniformity coefficient (also known as the power peak factor or hot spot factor) is calculated as follows.
The change in core axial power between loading and unloading axially non-uniform tubular MA transmutation rods of different designs is reflected in fig. 14. From the figure, the axial power of the reactor core can be effectively flattened through the reasonable non-uniform axial design of the transmutation rods and loading the transmutation rods into the reactor core. In four axial non-uniform schemes (the pipe wall thickness is 0.1 cm), the optimal flattening effect is scheme III, namely, a shaft uniformly divides a transmutation rod into five sections, the mass share of MA nuclides is sequentially 1%, 3% and 5% from two ends to the middle section, and the power peak shape under the scheme is greatly improved compared with the situation of no transmutation rod. In contrast, the flattening effect of the scheme II is insufficient, the axial power peak is obviously outwards spread towards two ends by the scheme I and the scheme IV, but the mass share of MA at two ends of the scheme I is lower, and the segments of the high MA mass share in the scheme IV are too concentrated, so that the relative power of the middle section of the scheme II is slightly lower. The axial power peak factor of each protocol was calculated as shown in table 1, and the axial power peak factor of protocol three was the lowest, 1.249.
TABLE 1 influence of axially non-uniform tubular MA transmutation rods on core axial Power Peak factor
Initial pile Scheme one Scheme II Scheme III Scheme IV
Power peak factor 1.666 1.391 1.461 1.249 1.390
The transmutation rods of the various schemes described in examples 1-22 were loaded into the core for burnup calculations and research, with a total burnup time of 540 days, simulating the cycle of one full power operation of a million kilowatt commercial pressurized water reactor. According to the burnup calculation result, the variation trend of the partial scheme MA nuclide density along with the burnup time step is as follows. The results show that the MA species in each protocol have different nuclear densities at the initial and final stages of burnup, but the overall trend of nuclear density change with burnup time step is the same, where 237 Np、 241 Am、 243 Am decreases with burnup time step, 244 cm increases with burn-up time step due to 237 Np、 241 Am、 243 Am can be converted and generated 244 Cm, leading to 244 Cm generation rate is greater than disappearance rate, thus 244 The total amount of Cm is not reduced and increased.
In addition, because the axially non-uniform tubular MA transmutation rod changes the mass share of MA nuclides in the segments, for example, the mass share of MA nuclides at two ends in the scheme II is 3 percent, the total MA loaded by the axially uniform transmutation rod is larger than that of the axially non-uniform transmutation rod. FIGS. 15, 16, 17, 18 and 19 are respectively of the non-uniform tubular MA transmutation rods of examples 1-4 237 Np、 241 Am、 243 Am、 244 Cm andMA nuclei density versus burnup curve.
The rate of transmutation of MA species decreases with increasing loading, so to determine the proper MA: UO 2 The ratio is calculated and researched by burning up to obtain three MA: UO 2 The transmutation rates of MA species at the ratios are shown in table 2. The results show that as the proportion of MA in the transmutation rod increases, the rate of MA transmutation decreases, but the total amount of transmutation increases. When MA/UO 2 At a MA mass fraction of 5% in the mixed material, the total transmutation rate is reduced by only about 5% relative to a MA mass fraction of 1%, but the total MA loading is increased by a factor of 5. The transmutation rate calculation method is shown in the following formula.
Adding to a transmutation material having a mass fraction of MA of 5% in a transmutation rod 6 LiD respectively calculate 6 The MA transmutation rates for five cases, lin=1:9, 2:8, 3:7, 4:6, 5:5 are shown in table 3. The results showed that with 6 LiD: MA ratio is increased, total transmutation rate of MA nuclides is gradually reduced, but 244 The transmutation rate of Cm is significantly increased due to 6 The LiD converts partial low-energy neutrons into high-energy neutrons, and the fission section of the MA nuclide in a high-energy region is larger, so that the direct fission rate of the MA nuclide is improved, and the absorption capture rate is reduced.
The solid central layer of the non-uniform tubular MA transmutation rod is changed into the central layer of a hollow structure, and the calculation and the research are carried out on the transmutation rod 6 Lin: transmutation performance at ma=1:9, 2:8, 3:7, 4:6, 5:5, thickness at 0.05cm, 0.1cm, 0.15cm, 0.2cm, 0.25cm, 0.3cm, five 6 LiD: MA ratio 237 Np、 241 Am、 243 Am (Am) 244 The transmutation rates of Cm for the four species are shown in fig. 20-24. The result shows that the space self-shielding effect has very remarkable influence on MA transmutation, namely the MA transmutation rate can be reduced along with the increase of the thickness of the pipe wall, because the thin pipe wall is easier to penetrate by neutrons, neutrons which are incident to a position deeper than the pipe wall are reduced, and MA nuclides which are positioned at a shallower position are easier to transmute. The thinner the tube wall, the higher the rate of MA species transmutation, but also the reduction of MA loading.
The flux/power distribution of the reactor core in the axial direction is also characterized by 'middle high and two sides low', and the neutron flux density is higher nearer to the center of the reactor core, so that in order to further improve the transmutation performance of transmutation rods, the transmutation rods are divided into three, five and seven sections in the axial direction, and the fuel consumption calculation research is carried out by dividing four axial non-uniformization schemes, wherein the scheme is as follows: axially dividing into three sections, wherein the mass fraction of MA nuclides at two ends is 1%, and the mass fraction of MA nuclides at the middle section is 5%; scheme II: axially dividing the material into three sections, wherein the mass fraction of MA nuclides at two ends is 3%, and the mass fraction of MA nuclides at the middle section is 5%; scheme III: axially dividing into five sections, wherein the sections from two ends to the middle section, and the mass ratio of MA nuclides is sequentially 1%, 3% and 5%; scheme 4: the axial direction is divided into seven sections, and the proportion of MA nuclides is 0%, 1%, 3% and 5% in sequence from two ends to the middle section. The effect of the axial non-uniformity scheme on the MA species transmutation rate is shown in table 4.
The results show that scheme two under each wall thickness in the four schemes 244 The Cm transmutation rates are all highest, which shows that the MA nuclide direct fission rate is higher under the scheme, the total transmutation rate of the scheme II is highest when the pipe wall thickness is 0.1Cm and 0.15Cm, the total transmutation rate of the scheme III is highest when the pipe wall thickness is 0.05Cm and 0.2Cm, and the flattening of the scheme III to axial power is better than that of the scheme II from the aspect of flattening power. Taken together, if desiredThe scheme II can be used as an optimal scheme, and the scheme III is an optimal scheme if the reactor core axial power is flattened better while the transmutation performance is tracked.
According to transmutation rod, loading and adding 6 The transmutation performance of different schemes in table 5 and the transmutation effect of partial schemes in table 6 are manufactured by comparing the transmutation rates of partial research schemes according to the research ideas of the transmutation rod of LiD, the change of the pipe wall thickness and the axial non-uniformity of the transmutation rod, wherein the pipe wall thickness adopted by the axial non-uniform scheme is 0.1cm. It can be seen that the total transmutation rate of MA nuclides can be improved by making the transmutation rod into a hollow transmutation tube or making a non-uniform design in the axial direction 6 The solid transmutation rod with the ratio of LiD to MA of 1:9 is improved to an axial non-uniform scheme II or III (the thickness of the tube wall is 0.1 cm), so that the total transmutation rate of MA nuclides can be improved by more than 10%.
According to the condition that the transmutation rate is along with the thickness of the pipe wall, the trend of the change of the transmutation rate influenced by the space self-shielding effect is obvious, namely the thinner the pipe wall is, the higher the total transmutation rate is, and according to the actual transmutation condition, the total MA loading is increased along with the increase of the thickness of the pipe wall, so that 6 LiD, MA=1:9, transmutation rod with wall thickness of 0.05cm, with outer diameter of 0.4096cm, inner diameter of 0.3596cm, transmutation material density of 10.3g/cm 3 The length of each transmutation rod is 365.76cm, and the mass share of MA nuclides in each transmutation rod is 0.04972, so that the total mass of MA nuclides in each transmutation rod is as follows:
π×(0.4096 2 -0.3596 2 )×365.76×10.3×0.04972＝22.63204g
the total mass of MA in the reactor core is:
22.63204×1536/1000＝34.75998kg
after 540 days of transmutation, the total mass of MA transmutation of the reactor core is as follows:
34.75998×57.83％＝20.10219kg
while the common pressurized water reactor generates 25.166kg of MA nuclides every year, the total amount of MA which can be transmuted under the scheme is less than the annual MA yield of one common pressurized water reactor, but if the pipe wall thickness is increased to 0.2cm, and the second axial non-uniform scheme is adopted, the MA nuclides can be transmuted by about 47kg, the transmutation total amount achieved by the scheme is close to the annual MA yield of two common pressurized water reactors, and the transmutation effect is obviously improved.
The number of equipment and the scale of processing described herein are intended to simplify the description of the present invention. Applications, modifications and variations of the present invention will be readily apparent to those skilled in the art.
Although embodiments of the present invention have been disclosed above, it is not limited to the details and embodiments shown and described, it is well suited to various fields of use, and further modifications may be readily made by those skilled in the art without departing from the general concepts defined by the claims and the equivalents thereof, and therefore the invention is not limited to the specific details and examples shown and described herein.

Claims (7)

1. A non-uniform tubular MA transmutation rod with flattened core axial power functionality, comprising:
a central layer positioned at the center of the heterogeneous tubular MA transmutation rod, the outside of the central layer is provided with 6 LiD/MA/UO 2 A mixed fuel layer, said 6 LiD/MA/UO 2 An air gap layer is arranged outside the mixed fuel layer, and a zirconium alloy cladding is arranged outside the air gap layer;
the non-uniform tubular MA transmutation rod is axially provided with odd sections 6 LiD/MA/UO 2 A mixed fuel layer, and two adjacent sections 6 LiD/MA/UO 2 The mass share of MA nuclides in the mixed fuel layers is different, and each section is from the upper end of the heterogeneous tubular MA transmutation rod to the middle position 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is gradually increased; MA transmutation from non-uniform tubeIntermediate position to lower end of rod, each section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is gradually decreased; 6 the mass ratio of LiD to MA nuclide is fixed at 1:9;
the central layer is of a solid structure or a hollow void structure.
2. The non-uniform tubular MA transmutation rod with flattened core axial power function of claim 1, wherein said non-uniform tubular MA transmutation rod is axially provided with three sections of 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 Mixed fuel layer, second section 6 LiD/MA/UO 2 Mixed fuel bed and third section 6 LiD/MA/UO 2 A mixed fuel layer, wherein the first section 6 LiD/MA/UO 2 Mixed fuel bed and third section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 1% -3%, and the second section is that 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 5 percent, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
3. The non-uniform tubular MA transmutation rod with flattened core axial power function of claim 1, wherein said non-uniform tubular MA transmutation rod is axially provided with five segments 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 Mixed fuel layer, second section 6 LiD/MA/UO 2 Mixed fuel layer, third section 6 LiD/MA/UO 2 Mixed fuel layer, fourth section 6 LiD/MA/UO 2 Mixed fuel bed and fifth section 6 LiD/MA/UO 2 A mixed fuel layer, wherein the first section 6 LiD/MA/UO 2 Mixed fuel bed and fifth section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 1 percent, and the second section 6 LiD/MA/UO 2 Mixed fuel layer and fourth stage 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 3 percent, and the third section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 5 percent, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
4. The non-uniform tubular MA transmutation rod with flattened core axial power function of claim 1, wherein said non-uniform tubular MA transmutation rod is axially provided with seven segments 6 LiD/MA/UO 2 The mixed fuel layer is sequentially recorded as a first section from the upper end to the lower end of the heterogeneous tubular MA transmutation rod 6 LiD/MA/UO 2 Mixed fuel layer, second section 6 LiD/MA/UO 2 Mixed fuel layer, third section 6 LiD/MA/UO 2 Mixed fuel layer, fourth section 6 LiD/MA/UO 2 Mixed fuel layer, fifth section 6 LiD/MA/UO 2 Mixed fuel layer, sixth section 6 LiD/MA/UO 2 Mixed fuel layer and seventh section 6 LiD/MA/UO 2 A mixed fuel layer, wherein the first section 6 LiD/MA/UO 2 Mixed fuel layer and seventh section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 0 percent, and the second section 6 LiD/MA/UO 2 Mixed fuel layer and sixth section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 1 percent, and the third section 6 LiD/MA/UO 2 Mixed fuel bed and fifth section 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 3%, and the fourth section is that 6 LiD/MA/UO 2 The proportion of MA nuclides in the mixed fuel layer is 5 percent, 6 the mass ratio of LiD to MA nuclide is fixed at 1:9.
5. The non-uniform tubular MA transmutation rod with flattened core axial power functionality of claim 1, wherein said core is 6 LiD/MA/UO 2 The composition of MA nuclides in the mixed fuel layer comprises 237 Np、 241 Am、 243 Am, and 244 cm, where 237 The mass ratio of Np is 56.36%, 241 am mass ratio26.48 percent, 243 am is 12.03% by mass, 244 the mass ratio of Cm is 5.12%.
6. The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core of claim 1, wherein 2 non-uniform tubular MA transmutation rods are respectively loaded at the central positions of the x-axis direction and the y-axis direction of the fuel assembly, and 3 non-uniform tubular MA transmutation rods are respectively loaded at the four corners of the fuel assembly, namely 16 non-uniform tubular MA transmutation rods are loaded in one fuel assembly; 36 groups of fuel assemblies with 3.1% fuel enrichment degree are loaded near the central position in the reactor core, and 60 groups of fuel assemblies with 3.1% fuel enrichment degree except the central position are loaded, namely 1536 heterogeneous tube type MA transmutation rods are loaded in one reactor core.
7. The non-uniform tubular MA transmutation rod with the function of flattening the axial power of the reactor core of claim 1, wherein the thickness of the tube wall of the non-uniform tubular MA transmutation rod is 0.05 cm-0.3 cm.
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Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3039944A (en) * 1959-05-13 1962-06-19 Zumwalt Lloyd Robert Fuel element
WO2008051180A2 (en) * 2005-05-26 2008-05-02 Spindletop Corporation Method and apparatus for acceleration-induced reactions in materials containing deuterium
JP2011169710A (en) * 2010-02-18 2011-09-01 Hitachi-Ge Nuclear Energy Ltd Core and fuel assembly in fast breeder reactor
JP2013050366A (en) * 2011-08-31 2013-03-14 Hitachi Ltd Fast reactor core
CN108470589A (en) * 2018-05-02 2018-08-31 中国科学技术大学 It is a kind of can transmuting simultaneously time actinium series nucleic and long-lived fission product the fast critical reactor core of hot mixing power spectrum
CN108550405A (en) * 2018-03-23 2018-09-18 中山大学 Mox fuel stick, mox fuel component and the method for flattening axial power
RU2733900C1 (en) * 2020-03-06 2020-10-08 Государственная корпорация по атомной энергии "Росатом" Fast liquid-salt reactor

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20070133733A1 (en) * 2005-12-07 2007-06-14 Liviu Popa-Simil Method for developing nuclear fuel and its application
FR2978697B1 (en) * 2011-08-01 2014-05-16 Commissariat Energie Atomique IMPROVED MULTILAYER TUBE OF CERAMIC MATRIX COMPOSITE MATERIAL, RESULTING NUCLEAR FUEL SLEEVE AND METHODS OF MANUFACTURING THE SAME
US20130083878A1 (en) * 2011-10-03 2013-04-04 Mark Massie Nuclear reactors and related methods and apparatus
US20190139651A1 (en) * 2017-06-09 2019-05-09 Innoven Energy Llc High Radiation Efficiency Non Fissile Shell for ICF

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3039944A (en) * 1959-05-13 1962-06-19 Zumwalt Lloyd Robert Fuel element
WO2008051180A2 (en) * 2005-05-26 2008-05-02 Spindletop Corporation Method and apparatus for acceleration-induced reactions in materials containing deuterium
JP2011169710A (en) * 2010-02-18 2011-09-01 Hitachi-Ge Nuclear Energy Ltd Core and fuel assembly in fast breeder reactor
JP2013050366A (en) * 2011-08-31 2013-03-14 Hitachi Ltd Fast reactor core
CN108550405A (en) * 2018-03-23 2018-09-18 中山大学 Mox fuel stick, mox fuel component and the method for flattening axial power
CN108470589A (en) * 2018-05-02 2018-08-31 中国科学技术大学 It is a kind of can transmuting simultaneously time actinium series nucleic and long-lived fission product the fast critical reactor core of hot mixing power spectrum
RU2733900C1 (en) * 2020-03-06 2020-10-08 Государственная корпорация по атомной энергии "Росатом" Fast liquid-salt reactor

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
"HFETR 6LiD转换器内聚变谱中子源强分析";孙寿华 等;《核聚变与等离子体物理》;全文 *

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