CN103366852A - Reactor core of high flux thermal neutron reactor for transmutation - Google Patents
Reactor core of high flux thermal neutron reactor for transmutation Download PDFInfo
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- CN103366852A CN103366852A CN2012100866999A CN201210086699A CN103366852A CN 103366852 A CN103366852 A CN 103366852A CN 2012100866999 A CN2012100866999 A CN 2012100866999A CN 201210086699 A CN201210086699 A CN 201210086699A CN 103366852 A CN103366852 A CN 103366852A
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Abstract
The invention discloses a reactor core of a high flux thermal neutron reactor for transmutation and belongs to the nuclear engineering technology field. The reactor core of the thermal neutron reactor is cylindrical and is formed by building a plurality of layers of fuel; each layer of fuel is shaped like a cylinder; a moderator is arranged between two adjacent layers of fuel; the reactor core comprises an internal layer and an external layer; and an internal layer thickness of the moderator is larger than an external layer thickness of the moderator so that neutrons can be better moderated. A quantity of layers of fuel in the external layer is greater than that of layers of fuel in the internal layer, and the thickness of layers of fuel in the external layer is larger than that of layers of fuel in the internal layer, so that sufficient neutron sources are provided to the internal layer to guarantee to obtain quite high thermal neutron flux in the internal layer. The high flux thermal neutron reactor uses the mature thermal reactor technology and the transmuting efficiency is high, so that much significance is provided to the steady development of the nuclear energy industry and the realization of the advanced nuclear fuel recycle system in our country.
Description
Technical field
The invention belongs to the nuclear engineering technical field, relate to a kind of high throughput thermally neutron pile reactor core for transmuting.
Background technology
The extensive development of nuclear power provides a large amount of clean type energy to the mankind, has satisfied society and resident living needs, but has also brought corresponding society and environmental problem when developing.Wherein one of problems of concern of the public is exactly how to dispose a large amount of high radioactivity nuclear wastes, particularly long-life high-level waste in the Nuclear Power Station's Exhausted Fuels.Long-life high-level waste in the spentnuclear fuel comprises
237Np,
241Am,
242MAm,
243Am,
243Cm,
244Cm reaches
245The Minor Actinides such as Cm (Minor Actinides, be called for short MA) and
99Tc,
129The long-life fission products (LLFP) such as I, they have consisted of tellurian and the main long-term radiological hazard of human environment.Therefore, realize the sustainable development of nuclear energy, one of major issue must be properly settled the aftertreatment problem of long-life high-level waste in the spentnuclear fuel exactly.
At present the mode of nuclear fuel cycle mainly contains two kinds in the world, and (1) " disposable by " (Once-through-cycle) is about to from nuclear power station unloading spentnuclear fuel out and buries disposal through directly carrying out geology after storing, solidifying; (2) " aftertreatment nuclear fuel cycle " (Reprocessing-fuel-cycle), be about to spentnuclear fuel through separating treatment, the nucleic such as U, Pu are wherein reclaimed, again be processed into nuclear fuel (such as mixed oxide fuel mixed oxide fuel, be called for short MOX), reuse, the long-life high radioactivity nucleic of separating is carried out geology bury disposal after the processing such as glass solidification." aftertreatment nuclear fuel cycle " can reclaim wherein, and the nucleic such as part uranium, plutonium carry out recycling, disposal route with respect to " disposable passing through ", the utilization factor of the resources such as the uranium that improves to a certain extent, plutonium, but therefore the method for disposal that it still adopts geology to bury to the disposal options of high-level waste still exists long-term potential radioactivity hidden danger.
The transmuting technology is present unique method that shortens the radioactive nuclide life-span, the transmuting technology refers to that the high nucleic of putting of long-life passes through neutron irradiation in neutron field, fission, capture etc. and to change into other without the nucleic process of harm after the reaction, purpose is to make the long-life nucleic convert short life or stable nuclide to, thereby eliminates Long-lived Radionuclides to the harm of ecologic environment.Can provide the transmuting facility of neutron source to comprise subcritical assembly (ADS) and other neutron source of thermal-neutron reactor, fast neutron reactor and Accelerator driven.Wherein technology the most ripe, be thermal reactor in the maximum heap type of operation, the research of therefore carrying out thermal reactor transmuting technology is significant, we have proposed to be exclusively used in the thermal reactor of transmuting-high throughput thermally neutron pile on the basis of the research of transmuting at home and abroad.
Summary of the invention
The present invention is directed to the deficiency of prior art transmuting MA nucleic ability, a kind of high throughput thermally neutron pile for transmuting is provided.
A kind of high throughput thermally neutron pile reactor core for transmuting, this thermal-neutron reactor reactor core is cylindrical, built by multilayer fuel, every grate firing material is cylindrical shape, it is moderator between the adjacent fuel bed, reactor core is divided into internal layer and outer two parts, and wherein every layer of the internal layer outer field every layer of moderator thickness of moderator Thickness Ratio is large, makes neutron obtain better slowing down; The outer fuel number of plies is more than the internal layer fuel number of plies, and every grate firing material thickness is thick than every grate firing material of internal layer, for internal layer provides enough neutron source, thereby guarantees to obtain higher thermal neutron flux at internal layer.When reactor core is processed the long-life during high-level waste, the wherein part of fuel layer of internal layer is replaced with the long-life high-level waste.
Described moderator is light-water or heavy water.
Described fuel is MOX or UO
2Fuel.
Described long-life high-level waste is MA.
A kind of preferred scheme: internal layer has 36 grate firing material, and skin has 60 grate firing material, and the thickness of the every grate firing material of its ectomesoderm is 0.125cm, and the thickness of every layer of moderator is 0.125cm, and the thickness of every layer of moderator of internal layer is 0.4cm, and every grate firing material thickness is 0.1cm.When reactor core is processed MA, the 1st, 16 and 31 grate firing material of internal layer are replaced with MA.
Beneficial effect of the present invention is: the transmuting efficient of high throughput thermally neutron pile of the present invention can reach 6.3%, so the efficient of high throughput thermally neutron pile transmuting MA will be higher than fast reactor.The neutron flux of tradition thermal reactor (mainly being presurized water reactor) is low, can not take full advantage of the MA nucleic and capture the fission product that neutron generates, so the efficient of transmuting MA is very low, only has about 1%.What the high throughput thermally neutron pile adopted is ripe thermal reactor technology, and transmuting efficient is high, significant to the realization of the healthy and stable development of China's nuclear energy industry and advanced nuclear fuel cycle system.
Description of drawings
Fig. 1 high throughput thermally neutron pile layer structure schematic diagram;
Fig. 2 high throughput thermally neutron pile endothecium structure schematic diagram;
Fig. 3 is the one-piece construction of high throughput thermally neutron pile;
Fig. 4 high throughput thermally neutron pile longitdinal cross-section diagram;
The layout of Fig. 5 high throughput thermally neutron pile transmuting layer.
Embodiment
The following examples can make those skilled in the art more fully understand the present invention, but do not limit the present invention in any way.
Embodiment 1
One, high throughput thermally neutron pile basic structure
A kind of high throughput thermally neutron pile reactor core for transmuting, this thermal-neutron reactor reactor core is cylindrical, built by multilayer fuel, every grate firing material is cylindrical shape, is the moderator layer between the adjacent fuel bed, reactor core is divided into internal layer and outer two parts, internal layer has 36 grate firing material, and skin has 60 grate firing material, and the thickness of the every grate firing material of its ectomesoderm is 0.125cm, the thickness of every layer of moderator is 0.125cm, as shown in Figure 1; In order to obtain higher thermal neutron flux at the reactor core internal layer, the thickness of every layer of moderator of internal layer is 0.4cm, and every grate firing material thickness is 0.1cm, and the internal diameter of innermost layer fuel is 0.5cm, and the center is moderator, as shown in Figure 2.Described moderator is light-water.
Two, the basic parameter of high throughput thermally neutron pile reactor core
The basic parameter of high throughput thermally neutron pile core model is as shown in table 1 below, because the reactor core neutron flux is high, therefore can adopt mox fuel.When table 2 reaches critical for reactor core, the basic composition of reactor fuel, UO in the fuel
2Massfraction be 92%, UO wherein
2The enrichment of middle U-235 is 0.25%; PuO
2Content be to include among 8%, the Pu
238Pu,
239Pu,
240Pu,
241Pu,
242Five kinds of isotopes of Pu, its massfraction is respectively 4%, 54.4%, 22.8%, 11.8%, 7%.
Through analog computation, when reactor core was critical, neutron-flux density can reach 2.0 * 10
15N/cm
2S.
Table 1 high throughput thermally neutron pile reactor core important technological parameters
The fuel composition of table 2 high throughput thermally neutron pile
Three, the performance of high throughput thermally neutron pile transmuting MA
When adopting MOX to act as a fuel, the highneutronflux density reachable 2.0 * 10 of high flux epithermal reactor
15N/cm
2S.MA is made independent transmuting layer, the 1st, 16 and 31 grate firing material of internal layer are replaced with MA transmuting layer, as shown in Figure 5.
Table 3 is the proportion of composing of each nucleic in the MA transmuting layer.
Calculate by analysis MA transmuting layer in the high throughput thermally neutron pile through 300 days the irradiation after,
237Np,
241Am,
243The disappearance rate of Am is respectively 73.7%, 98.1%, 82.8%, but the disappearance rate of directly fissioning only is respectively 3.19%, 3.07%, 2.54%;
244Cm,
245Cm is through after shining, and its quality does not only reduce and also rolls up, and recruitment is respectively 68.1%, 1130%, and is as shown in table 4.The MA element has very large capture cross-section in thermal-neutron reactor, can capture neutron and generate fissile nuclide, and the neutron flux of high pass thermal-neutron reactor is very high, therefore can guarantee that fissile nuclide occurs to fission before the decay disappearance, calculate by statistics, quality through remaining heavy nucleus in the unloading MA layer out after the irradiation in 300 days is 3.31Kg (original bulk is 3.97Kg), the disappearance amount is 0.66Kg, the quality that wherein generates He is 0.41Kg, therefore the quality that disappears of must fissioning is 0.25, accounts for original bulk and gets 6.3%.The transmuting rate that is to say the high throughput thermally neutron pile can reach 6.3%, and is high more a lot of than the transmuting efficient of fast reactor etc.But unload after the irradiation in the MA transmuting layer out
238The Pu growing amount is very large, and the massfraction that accounts for transuranic element among the MA is 38%.
In addition, calculate by analysis, the mox fuel of high throughput thermally neutron pile is through behind 300 days irradiation
238The rate of destroying by fire of Pu nucleic is up to 63%, so we generate can be with reactor core transmuting MA the time
238The Pu nucleic burns in the high throughput thermally neutron pile as the part in the mox fuel.
Studies show that the general 4-5% of efficient of fast reactor transmuting MA nucleic both at home and abroad, and the transmuting efficient of high throughput thermally neutron pile can reach 6.3%, so the efficient of high throughput thermally neutron pile transmuting MA to be higher than fast reactor.The neutron flux of tradition thermal reactor (mainly being presurized water reactor) is low, can not take full advantage of the MA nucleic and capture the fission product that neutron generates, so the efficient of transmuting MA is very low, only has about 1%.What the high throughput thermally neutron pile adopted in a word is ripe thermal reactor technology, and transmuting efficient is high, significant to the realization of the healthy and stable development of China's nuclear energy industry and advanced nuclear fuel cycle system,
The ratio of each nucleic among the table 3MA
Show 4MA disappearance rate through each nucleic after the irradiation in 300 days in high throughput thermally neutron pile model
The above; only for the better embodiment of the present invention, but protection scope of the present invention is not limited to this, anyly is familiar with those skilled in the art in the technical scope that the present invention discloses; the variation that can expect easily or replacement all should be encompassed within protection scope of the present invention.Therefore, protection scope of the present invention should be as the criterion with the protection domain of claim.
Claims (6)
1. thermal-neutron reactor reactor core that is used for transmuting, it is characterized in that: this thermal-neutron reactor reactor core is cylindrical, built by multilayer fuel, every grate firing material is cylindrical shape, be moderator between the adjacent fuel bed, reactor core is divided into internal layer and outer two parts, and wherein every layer of the internal layer outer field every layer of moderator thickness of moderator Thickness Ratio is large, the outer fuel number of plies is more than the internal layer fuel number of plies, and every grate firing material thickness is thick than every grate firing material of internal layer; When reactor core is processed the long-life during high-level waste, the wherein part of fuel layer of internal layer is replaced with the long-life high-level waste.
2. thermal-neutron reactor reactor core according to claim 1, it is characterized in that: described moderator is light-water or heavy water.
3. thermal-neutron reactor reactor core according to claim 1, it is characterized in that: described fuel is MOX or UO
2Fuel.
4. thermal-neutron reactor reactor core according to claim 1, it is characterized in that: described long-life high-level waste is MA.
5. thermal-neutron reactor reactor core according to claim 1, it is characterized in that: internal layer has 36 grate firing material, skin has 60 grate firing material, the thickness of the every grate firing material of its ectomesoderm is 0.125cm, the thickness of every layer of moderator is 0.125cm, the thickness of every layer of moderator of internal layer is 0.4cm, and every grate firing material thickness is 0.1cm.
6. thermal-neutron reactor reactor core according to claim 5 is characterized in that: when reactor core is processed MA, the 1st, 16 and 31 grate firing material of internal layer are replaced with MA.
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107929958A (en) * | 2018-01-04 | 2018-04-20 | 北京新核医疗科技有限公司 | A kind of MNSR Reactor neutron therapy device |
| CN108780666A (en) * | 2015-12-15 | 2018-11-09 | 科利尔株式会社 | Radioactive nuclear reactor system can be eliminated |
| CN113488204A (en) * | 2021-07-12 | 2021-10-08 | 西南科技大学 | Casing type MA transmutation rod for fast neutron reactor |
| CN113643838A (en) * | 2021-07-27 | 2021-11-12 | 西南科技大学 | Non-uniform MA transmutation rod with function of flattening axial power of reactor core |
| CN114068043A (en) * | 2021-10-09 | 2022-02-18 | 中广核研究院有限公司 | Particulate dense fuel element |
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| CN1945751A (en) * | 2006-11-21 | 2007-04-11 | 中国原子能科学研究院 | Accelerator driven fast-thermally coupled subcritical reactor |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108780666A (en) * | 2015-12-15 | 2018-11-09 | 科利尔株式会社 | Radioactive nuclear reactor system can be eliminated |
| CN107929958A (en) * | 2018-01-04 | 2018-04-20 | 北京新核医疗科技有限公司 | A kind of MNSR Reactor neutron therapy device |
| CN113488204A (en) * | 2021-07-12 | 2021-10-08 | 西南科技大学 | Casing type MA transmutation rod for fast neutron reactor |
| CN113488204B (en) * | 2021-07-12 | 2023-07-25 | 西南科技大学 | Sleeve type MA transmutation rod for fast neutron reactor |
| CN113643838A (en) * | 2021-07-27 | 2021-11-12 | 西南科技大学 | Non-uniform MA transmutation rod with function of flattening axial power of reactor core |
| CN113643838B (en) * | 2021-07-27 | 2023-08-11 | 西南科技大学 | Heterogeneous MA transmutation rod with flattening reactor core axial power function |
| CN114068043A (en) * | 2021-10-09 | 2022-02-18 | 中广核研究院有限公司 | Particulate dense fuel element |
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