CN102194531A - Dual travelling wave partition burning method for fast reactor fuels - Google Patents
Dual travelling wave partition burning method for fast reactor fuels Download PDFInfo
- Publication number
- CN102194531A CN102194531A CN2010101304951A CN201010130495A CN102194531A CN 102194531 A CN102194531 A CN 102194531A CN 2010101304951 A CN2010101304951 A CN 2010101304951A CN 201010130495 A CN201010130495 A CN 201010130495A CN 102194531 A CN102194531 A CN 102194531A
- Authority
- CN
- China
- Prior art keywords
- reactor
- reactor core
- power
- district
- subregion
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Images
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to a partition burning method for nuclear reactor fuels and in particular relates to a dual travelling wave partition burning method for fast reactor fuels. The method comprises the following steps of: partitioning a reactor core of a fast reactor, and constructing a reactor starting region on the axial middle part of the reactor core; constructing an ignition position on the axial middle part of the reactor core of the fast reactor; and when the reactor core is stably operated, forming partitioned dual travelling waves, namely two main combustion regions. By the method, the values of two power peaks of the reactor core can be weakened by 25 percent respectively compared with the value of a single travelling wave power peak, but the total power of the reactor core is increased by 50 percent; moreover, the axial power distribution of the reactor core is flattened; the partial power peak is reduced; the average power and the total power of the reactor core are enhanced; the economical efficiency and the safety of the reactor as well as capability of maintaining integrality of materials in the reactor are improved; and thermotechnical hydraulic power of the reactor core is optimized. The method is particularly applied to a large million-kilowatts-class fast reactor nuclear power station.
Description
Technical field
The invention belongs to a kind of nuclear reactor fuel from the subregion combustion method, be specifically related to a kind of fast neutron reactor fuel dual-travel-wave from the subregion combustion method.
Background technology
The fuel of fast neutron reactor (fast reactor) has standing wave combustion system and row ripple combustion system from the subregion combustion system. is because row ripple combustion system can make the fast reactor of using it have unique advantage; ,《Nuclear Science andEngineering》2001139306-317“CANDLE：The new bum-up strateg”《Annals of Nuclear Energy》20083518-36“Design research of smalllong life CANDLE fast reactor” ( CANDLE ) ( TerraPower LLC ) 《TechnologyReview》2009242-44“Traveling-wave reactor”《Transactions ofthe American Nuclear Society》200898738“A First GenerationTraveling Wave Reactor” ( Traveling-Wave ) 。 The single file ripple is that the burning of reactor fuel is axially from one end to the other side being advanced with certain speed as candle from the fundamental starting point of subregion combustion system, its advantage is in whole burning interim arbitrary moment in longevity, and the power of reactor and reactivity all are invariable; Various performance parameters is interim all invariable in the longevity, realizes the radially height optimization of distribute power, thereby in steady-state operation, does not need burn control rod and driving mechanism thereof; And the phase in overlength longevity can realize by increasing core height easily; But the degree of depth is burned natural uranium, the weary uranium of light water reactor and thorium and be need not to reload; Have high inherent safety and economy.Because burning rate is invariable, so the phase in physics longevity of reactor core is about the height of reactor core and the ratio of burning rate.
The single file ripple is initially set up 1 fresh fuel district 1 and 1 axially, from top to bottom along it from the subregion combustion system and is opened heap district 2.As shown in Figure 3, the single file ripple makes reactor core be divided into fresh fuel district 1,3 three the physics combustion zones in main combustion zone 4 and spentnuclear fuel district automatically from the subregion combustion system.The axial a certain end that district 2 is structured in reactor core is piled in opening of reactor core, opens the heap action and also finishes at this end.After opening heap, only produce a neutron flux peak on reactor core is axial, i.e. burning row ripple.Burning row ripple is stablized propelling from reactor core one end to the other end.The single file ripple axially has only the combustion wave of advancing from subregion fast reactor reactor core, and local power peak is very high, causes cooling medium, involucrum and fuel temperature to produce very big rising in a relatively shorter axial direction part.The long-term integrity of material kept in this was unfavorable for piling, and the raising of reactor core average power and general power also can be subjected to the restriction of secure context.
Summary of the invention
The object of the present invention is to provide a kind of average power and general power that improves capable ripple fast reactor, improve the security of reactor and the integrality hold facility of the interior material of heap, the fast neutron reactor fuel dual-travel-wave of optimizing reactor core thermal-hydraulic performance is from the subregion combustion method.
Technical scheme of the present invention is as follows: a kind of fast neutron reactor fuel dual-travel-wave is from the subregion combustion method, and it comprises the steps:
Step 1: the reactor core to fast neutron reactor carries out subregion, and reactor core axially middle part structure opens the heap district;
Step 2: ignition location is arranged on the axial middle part that the fast neutron reactor reactor core opens the heap district.
Step 3: after reactor core enters steady-state operation, form dual-travel-wave, promptly form two main combustion zones from subregion.
It is specific as follows in the described step 1 reactor core of fast neutron reactor to be carried out subregion: reactor core axially is divided into 3 districts along it, axially makes up 1 and open the heap district in the middle part at reactor core, make up 2 fresh fuel districts at the axial two ends of reactor core.
Described concentration≤13% that opens the enriched uranium in heap district.
Effect of the present invention is: method of the present invention has been set up dual-travel-wave from the subregion notion of burning.At the single file ripple on the basis of subregion combustion system, flattening the reactor core axial power distributes, reduce local power peak, the average power and the general power of reactor have been improved, the peak value at two power peaks can respectively cut down 25% on the basis at single file wave power peak, but the reactor core general power increases by 50%, and has improved the integrality hold facility of material in the heap, has optimized the thermal-hydraulic performance of reactor core.When improving nuclear reactor safety and long-lived phase integrality, improved the economy of reactor, be specially adapted to the fast reactor nuclear power station of large-scale gigawatt higher level.
Description of drawings
Fig. 1 is that fast neutron reactor fuel dual-travel-wave of the present invention is from subregion combustion process synoptic diagram.
Fig. 2 is the CONCENTRATION DISTRIBUTION synoptic diagram that fast neutron reactor of the present invention opens main nucleic in the heap district.
Fig. 3 is that existing fast neutron reactor fuel single file ripple is from subregion combustion process synoptic diagram.
Among the figure: 1. fresh fuel district; 2. open the heap district; 3. spentnuclear fuel district; 4. main fuel district; X: reactor core is axial; Y: nuclide concentration direction from low to high.
Embodiment
Below in conjunction with drawings and Examples the present invention is described in further detail.
As shown in Figure 1, a kind of fast neutron reactor fuel dual-travel-wave of the present invention is carried out according to following steps from the subregion combustion method:
Step 1: the reactor core to fast neutron reactor carries out subregion, makes up 1 at the axial middle part of reactor core and opens heap district 2
Reactor core axially is divided into 3 districts along it, makes up 1 at the axial middle part of reactor core and open heap district 2, in 2 fresh fuel districts 1 of structure, the axial two ends of reactor core.
Step 2: ignition location is arranged on the axial middle part that the fast neutron reactor reactor core opens the heap district
Ignition location is arranged on the axial middle part that the fast neutron reactor reactor core opens heap district 2, lights the nuclear fuel that opens in the heap district 2.
Described concentration≤13% that opens the enriched uranium in heap district 2.
Can adopt prior art in opening heap district 2, to adjust enriched uranium concentration piecemeal, make the neutron flux that opens heap district 2 be distributed in the distribution of opening when piling the back near stable state combustion.
Step 3: after reactor core enters steady-state operation, form dual-travel-wave, promptly form two main combustion zones 4 from subregion
After reactor core enters steady-state operation, form dual-travel-wave automatically from subregion.Describedly be two neutron flux main combustion zone 4 in from subregion burning dual-travel-wave and distribute, the watt level and the shape of the capable ripple in two main combustion zones 4 are close, and the interior capable ripple in two main combustion zones 4 mutually independently.Form 1 spentnuclear fuel district 3 between two main combustion zones 4.Further burning along with nuclear fuel, two main combustion zones 4 axially are close at the uniform velocity to the negative line feed of reactor core two ends separately along reactor core, increase till the reactor core fission reaction that causes can't control oneself until the neutron leakage that causes near the axial two ends of reactor core because of fuel consumption and two main combustion zones 4.
Fast neutron reactor fuel dual-travel-wave of the present invention is from the foundation of subregion combustion method, the fuel composition that needs fast reactor fresh fuel district 1 mainly is the active low fuel material of the weary uranium isoreactivity of natural uranium or light water reactor, the reactivity in this district is very low, neutron flux is also very low, its significant feature is to utilize fast neutron at the boundary with main combustion zone 4 a large amount of U238 progressively to be changed into Pu239, for main combustion zone 4 provides easy fissioner.A large amount of Pu239 fissions that 4 of main combustion zones utilize fresh fuel district 1 to transform and generate are done work, and reactivity is very high, and local infinite medium multiplication constant can reach about 1.2, so the neutron flux in this district is very high.Spentnuclear fuel district 3 is along with the consumption of Pu239 and a large amount of fission products generate, and reactivity progressively reduces, and neutron flux also is reduced to the level in fresh fuel district 1.For avoiding reactive great fluctuation process, fresh fuel district 1 must adopt the insensitive natural uranium of thermal neutron, the weary uranium of light water reactor or the extremely low fertile material of enrichment.The fast neutron that main combustion zone 4 produces the only boundary in this district and fresh fuel district 1 transforms fertile material, requiring the interior fuel element of heap should try one's best under the situation of thermal-hydraulic conditions permit closely arranges, the neutron that increases breed fuel absorbs, the diffusion of control neutron.
Shown in the figure on Fig. 1 right side, during steady-state operation, reactor core axially has 5 physics burning subregions along it, 4,2 fresh fuel districts 1,3,2 main fuel districts, 1 spentnuclear fuel district, reactor core axially middle part is 1 spentnuclear fuel district 3,3 liang of outsides, spentnuclear fuel district have 1 main fuel district 4 respectively, and each 4 outside, main fuel district has 1 fresh fuel district 1 respectively.Shown in the figure in Fig. 1 left side, when just piling, reactor core is divided into 3 districts, and the fresh fuel district 1 that is positioned at the axial two ends of reactor core has 2, and the heap district 2 of opening that contains enriched uranium that is positioned at the reactor core middle part has 1.During stable state combustion, open heap district 2 and form main combustion zone, the enriched uranium that opens in the heap district 2 is distributed in distribution when opening the heap back just near stable state combustion by adjusting its concentration piecemeal, make the neutron flux that opens heap district 2.In fact be exactly in opening heap district 2 effect, the infinite medium multiplication constant that opens heap district 2 distributed just reach the approximation steady state distribution from opening the heap beginning by the main nucleic such as Pu239 of the main combustion zone 4 of the corresponding simulation of U235.
When the dual-travel-wave of fast neutron reactor moves with specific speed,, the observer moves along axial X of reactor core and main combustion zone 4 together with burning rate, and viewed axial neutron flux distributes and each nucleic Density Distribution does not change in time.
The CONCENTRATION DISTRIBUTION synoptic diagram that opens main nucleic in the heap district 2 as shown in Figure 2.Among the figure, the CONCENTRATION DISTRIBUTION of U238 in the heap district 2 is opened in curve a representative; The CONCENTRATION DISTRIBUTION of U235 in the heap district 2 is opened in curve b representative; Curve c representative is initially in order to the CONCENTRATION DISTRIBUTION of the niobium of simulation fission product effect; X is that reactor core is axial, and promptly directions X is represented the core height direction, Y direction indication nuclide concentration direction from low to high.To form two close but separate neutron flux peak shapes after reactor core starts at two peak value places of U235 concentration curve b and distribute, be i.e. burning row ripple.Open carry out of heap back along with burning, Pu239 will progressively transform automatically from a large amount of U238 and generate, substitute the initial U235 charging that progressively is consumed with certain enrichment, the generation of various fission products simultaneously is the progressively cross section effect of substitute niobium also, the burning of reactor core also will carry out the transition to the stable state combustion stage naturally, as shown in Figure 1.According to the nucleic kind that opens heap district 2 and the initial setting up of CONCENTRATION DISTRIBUTION, Coupled Dynamic self-equilibrating between the generation of generation, consumption and the fission product by fissile nuclide relation again, to make two burning row ripples keep its spatial form and amplitude size, be close to separately evenly reactor core axially on lentamente from the reactor core middle part to reactor core axial two ends negative line feed.
In conjunction with the accompanying drawings embodiments of the invention have been done detailed description above, but the present invention is not limited to the foregoing description, in the ken that those of ordinary skills possessed, can also under the prerequisite that does not break away from aim of the present invention, makes various variations.The content that is not described in detail in the instructions of the present invention all can adopt prior art.
Claims (3)
1. a fast neutron reactor fuel dual-travel-wave is from the subregion combustion method, and it is characterized in that: it comprises the steps:
Step 1: the reactor core to fast neutron reactor carries out subregion, and reactor core axially middle part structure opens heap district (2);
Step 2: ignition location is arranged on the axial middle part that the fast neutron reactor reactor core opens the heap district.
Step 3: after reactor core enters steady-state operation, form dual-travel-wave, promptly form two main combustion zones (4) from subregion.
2. a kind of fast neutron reactor fuel dual-travel-wave according to claim 1 is from the subregion combustion method, it is characterized in that: it is specific as follows in the described step 1 reactor core of fast neutron reactor to be carried out subregion: reactor core axially is divided into 3 districts along it, make up 1 at the axial middle part of reactor core and open heap district (2), in structure 2 fresh fuel districts (1), the axial two ends of reactor core.
3. a kind of fast neutron reactor fuel dual-travel-wave according to claim 1 and 2 is characterized in that from the subregion combustion method: described concentration≤13% that opens the enriched uranium in heap district (2).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010101304951A CN102194531A (en) | 2010-03-11 | 2010-03-11 | Dual travelling wave partition burning method for fast reactor fuels |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010101304951A CN102194531A (en) | 2010-03-11 | 2010-03-11 | Dual travelling wave partition burning method for fast reactor fuels |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102194531A true CN102194531A (en) | 2011-09-21 |
Family
ID=44602440
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2010101304951A Pending CN102194531A (en) | 2010-03-11 | 2010-03-11 | Dual travelling wave partition burning method for fast reactor fuels |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102194531A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105427898A (en) * | 2015-12-09 | 2016-03-23 | 中国原子能科学研究院 | Multiple-partition mode traveling wave type burning long-life reactor core |
| CN109615110A (en) * | 2018-11-13 | 2019-04-12 | 中国原子能科学研究院 | Fast reactor heap in-core coolant flow partition method |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0387891A2 (en) * | 1989-03-17 | 1990-09-19 | Hitachi, Ltd. | Fast neutron reactor and method of refueling |
| CN1069596A (en) * | 1991-08-20 | 1993-03-03 | 法玛通公司 | The inner structure of fast neutron nuclear reaction heap |
| EP1693855A2 (en) * | 2003-10-06 | 2006-08-23 | The Federal State Unitarian Enterprise " A.A. Bochvar All-Russia Research Institute of Inorganic Materials" | Fuel element for a fast neutron reactor (variants) and a cladding for the production thereof |
| CN101584009A (en) * | 2006-11-28 | 2009-11-18 | 希尔莱特有限责任公司 | Method and system for providing fuel in a nuclear reactor |
-
2010
- 2010-03-11 CN CN2010101304951A patent/CN102194531A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0387891A2 (en) * | 1989-03-17 | 1990-09-19 | Hitachi, Ltd. | Fast neutron reactor and method of refueling |
| CN1069596A (en) * | 1991-08-20 | 1993-03-03 | 法玛通公司 | The inner structure of fast neutron nuclear reaction heap |
| EP1693855A2 (en) * | 2003-10-06 | 2006-08-23 | The Federal State Unitarian Enterprise " A.A. Bochvar All-Russia Research Institute of Inorganic Materials" | Fuel element for a fast neutron reactor (variants) and a cladding for the production thereof |
| CN101584009A (en) * | 2006-11-28 | 2009-11-18 | 希尔莱特有限责任公司 | Method and system for providing fuel in a nuclear reactor |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105427898A (en) * | 2015-12-09 | 2016-03-23 | 中国原子能科学研究院 | Multiple-partition mode traveling wave type burning long-life reactor core |
| CN105427898B (en) * | 2015-12-09 | 2017-09-12 | 中国原子能科学研究院 | A kind of travelling-wave-type of multi partition pattern burns long core life |
| CN109615110A (en) * | 2018-11-13 | 2019-04-12 | 中国原子能科学研究院 | Fast reactor heap in-core coolant flow partition method |
| CN109615110B (en) * | 2018-11-13 | 2022-12-13 | 中国原子能科学研究院 | Fast reactor core coolant flow partitioning method |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103886921B (en) | A kind of full molten salt fuel hybrid reactor system of Th-U self-sustaining cycle and operation method thereof | |
| CN1945751B (en) | Accelerator driven fast-thermally coupled subcritical reactor | |
| Su’ud et al. | The prospect of gas cooled fast reactors for long life reactors with natural uranium as fuel cycle input | |
| JPS61111488A (en) | Fuel load for core of nuclear reactor and operating method thereof | |
| CN103299374A (en) | Nuclear reactor | |
| JP3433230B2 (en) | Reactor core and nuclear fuel material replacement method in the core | |
| CN102194531A (en) | Dual travelling wave partition burning method for fast reactor fuels | |
| CN103886918B (en) | Utilize hybrid reactor system and the operation method of water-cooled thorium-uranium fuel module arranged crosswise | |
| RU2541516C1 (en) | Operating method of nuclear reactor in thorium fuel cycle with extended reproduction of isotope 233u | |
| CN105427898B (en) | A kind of travelling-wave-type of multi partition pattern burns long core life | |
| Su’ud et al. | Modified CANDLE burnup calculation system, its evolution, and future development | |
| Monado et al. | Power flattening on modified CANDLE small long life gas-cooled fast reactor | |
| Okawa et al. | Design study on Pb-208 cooled CANDLE burning reactors toward practical application for future nuclear energy source | |
| Fareha et al. | Design Study of 600 MWt Long Life Modular Gas Cooled Fast Reactors | |
| CN104064228A (en) | Reactor actuation area for traveling wave reactor and manufacturing method for reactor actuation area of traveling wave reactor | |
| CN104021826A (en) | Method for designing axial travelling wave reactor starting area | |
| Su’ud et al. | Desain study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using special shuffling strategy in radial direction | |
| Yapıcı et al. | Neutronic analysis of a moderated (D, T) fusion driven hybrid blanket | |
| KR20140096807A (en) | Ultra-long Cycle Fast Reactor Using Spent Fuel | |
| JP2003107183A (en) | Mox fuel assembly for thermal neutron reactor | |
| CN204087815U (en) | The fusion-fission hybrid reactor covering fuel region that modular drives based on Z constriction | |
| Ariani et al. | Effect of Fuel Fraction on Small Modified CANDLE Burn‐up Based Gas Cooled Fast Reactors | |
| Widiawati et al. | Neutronic Analysis of Lead208-Bismuth Eutectic-Cooled Modified CANDLE Reactor with Core Geometry Variations | |
| CN113488205B (en) | Non-uniform tubular MA transmutation rod with function of flattening axial power of reactor core | |
| Zaki et al. | Modified CANDLE burnup scheme and its application for long life Pb-Bi cooled fast reactor with natural uranium as fuel cycle input |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C02 | Deemed withdrawal of patent application after publication (patent law 2001) | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20110921 |