JPS5934194A - 原子炉の炉心性能計算装置 - Google Patents
原子炉の炉心性能計算装置Info
- Publication number
- JPS5934194A JPS5934194A JP57144181A JP14418182A JPS5934194A JP S5934194 A JPS5934194 A JP S5934194A JP 57144181 A JP57144181 A JP 57144181A JP 14418182 A JP14418182 A JP 14418182A JP S5934194 A JPS5934194 A JP S5934194A
- Authority
- JP
- Japan
- Prior art keywords
- xenon
- iodine
- output
- concentration
- calculation
- 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.)
- Granted
Links
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 claims description 72
- 229910052740 iodine Inorganic materials 0.000 claims description 72
- 239000011630 iodine Substances 0.000 claims description 72
- 229910052724 xenon Inorganic materials 0.000 claims description 70
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 claims description 70
- 238000004364 calculation method Methods 0.000 claims description 61
- 238000009826 distribution Methods 0.000 claims description 59
- 238000003860 storage Methods 0.000 claims description 29
- 230000004907 flux Effects 0.000 claims description 7
- 238000005259 measurement Methods 0.000 claims description 3
- 230000001186 cumulative effect Effects 0.000 claims 1
- 238000012544 monitoring process Methods 0.000 description 11
- 238000000034 method Methods 0.000 description 9
- 230000004992 fission Effects 0.000 description 7
- 238000007796 conventional method Methods 0.000 description 6
- 230000008878 coupling Effects 0.000 description 6
- 238000010168 coupling process Methods 0.000 description 6
- 238000005859 coupling reaction Methods 0.000 description 6
- 238000004519 manufacturing process Methods 0.000 description 3
- 230000008859 change Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000004044 response Effects 0.000 description 2
- DSSYKIVIOFKYAU-XCBNKYQSSA-N (R)-camphor Chemical compound C1C[C@@]2(C)C(=O)C[C@@H]1C2(C)C DSSYKIVIOFKYAU-XCBNKYQSSA-N 0.000 description 1
- 241000723346 Cinnamomum camphora Species 0.000 description 1
- 241000257465 Echinoidea Species 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 229960000846 camphor Drugs 0.000 description 1
- 229930008380 camphor Natural products 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000001747 exhibiting effect Effects 0.000 description 1
- 230000036541 health Effects 0.000 description 1
- 238000011056 performance test Methods 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 230000004043 responsiveness Effects 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 210000002784 stomach Anatomy 0.000 description 1
- 230000002123 temporal effect Effects 0.000 description 1
- 239000011800 void material Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57144181A JPS5934194A (ja) | 1982-08-20 | 1982-08-20 | 原子炉の炉心性能計算装置 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57144181A JPS5934194A (ja) | 1982-08-20 | 1982-08-20 | 原子炉の炉心性能計算装置 |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS5934194A true JPS5934194A (ja) | 1984-02-24 |
JPH0444708B2 JPH0444708B2 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) | 1992-07-22 |
Family
ID=15356078
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP57144181A Granted JPS5934194A (ja) | 1982-08-20 | 1982-08-20 | 原子炉の炉心性能計算装置 |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS5934194A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2013505460A (ja) * | 2009-09-23 | 2013-02-14 | シーレイト リミテッド ライアビリティー カンパニー | 原子核分裂リアクターにおける物質の動き |
US10325689B2 (en) | 2013-11-21 | 2019-06-18 | Terrapower, Llc | Method and system for generating a nuclear reactor core loading distribution |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5439795A (en) * | 1977-09-06 | 1979-03-27 | Nippon Atom Ind Group Co Ltd | Core output predictiting device for atomic power plant |
JPS57125397A (en) * | 1981-01-28 | 1982-08-04 | Nippon Atomic Ind Group Co | Device for forecasting reactor core state of atomic power plant |
-
1982
- 1982-08-20 JP JP57144181A patent/JPS5934194A/ja active Granted
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5439795A (en) * | 1977-09-06 | 1979-03-27 | Nippon Atom Ind Group Co Ltd | Core output predictiting device for atomic power plant |
JPS57125397A (en) * | 1981-01-28 | 1982-08-04 | Nippon Atomic Ind Group Co | Device for forecasting reactor core state of atomic power plant |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2013505460A (ja) * | 2009-09-23 | 2013-02-14 | シーレイト リミテッド ライアビリティー カンパニー | 原子核分裂リアクターにおける物質の動き |
EP2481056A4 (en) * | 2009-09-23 | 2015-03-18 | Terrapower Llc | MOVEMENT OF MATERIALS IN A CORE REACTOR |
JP2016048261A (ja) * | 2009-09-23 | 2016-04-07 | テラパワー, エルエルシー | 原子核分裂リアクターにおける物質の動き |
US9576688B2 (en) | 2009-09-23 | 2017-02-21 | Terrapower, Llc | Movement of materials in a nuclear reactor |
US10325689B2 (en) | 2013-11-21 | 2019-06-18 | Terrapower, Llc | Method and system for generating a nuclear reactor core loading distribution |
US10566100B2 (en) | 2013-11-21 | 2020-02-18 | Terrapower, Llc | Method and system for generating a nuclear reactor core loading distribution |
US10593436B2 (en) | 2013-11-21 | 2020-03-17 | Terrapower, Llc | Method and system for generating a nuclear reactor core loading distribution |
Also Published As
Publication number | Publication date |
---|---|
JPH0444708B2 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) | 1992-07-22 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
RU2550689C2 (ru) | Способ содействия работе ядерного реактора | |
EP3896703B1 (en) | Method of providing bwr fuel pellets comprising determining u-235 enrichment levels determined by a computer-implemented simulation such that crud deposition does not occur under pre-determined boundary conditions | |
CN105006259A (zh) | 一种核电厂堆芯损伤评价方法 | |
Lu et al. | An efficient 1-D thermal stratification model for pool-type sodium-cooled fast reactors | |
JPS5934194A (ja) | 原子炉の炉心性能計算装置 | |
Marcum et al. | Benchmark comparison of experimental data with thermal-hydraulic codes RELAP5-3D and TRACE for a RIA transient scenario | |
Evitts et al. | Modelling Crevice Corrosion | |
Antonopoulos-Domis et al. | Moderator temperature coefficient of reactivity in Pressurized Water Reactors: theoretical investigation and numerical simulations | |
JPH0772282A (ja) | 原子炉の炉心性能推定方法およびその装置 | |
JPS63290994A (ja) | 炉心性能計算装置 | |
Lymperea et al. | Assessment of RELAP5/MOD3. 3 Against Single Rod Reflooding Experiments | |
Gandini | The heuristically-based generalized perturbation theory | |
Saikina et al. | Validation of the Severe Accident Module of the EUCLID/V2 Integral Code on the Basis of Experiments on a Failure of Simulators of Single Fuel Rods and Fuel Assemblies | |
Kale et al. | Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC” | |
Hainoun et al. | Dynamic analysis of the closed-loop transfer function in the miniature neutron source reactor (MNSR) | |
Werner et al. | Finite element analysis of transient heat conduction with moving convective boundaries | |
JPH06118193A (ja) | 原子炉炉心核特性模擬装置 | |
Robinson et al. | DETERMINATION OF THE VOID FRACTION IN THE MSRE USING SMALL INDUCED PRESSURE PERTURBATIONS. | |
Singer et al. | Response of EBR-II to a complete loss of primary forced flow during power operation | |
Abernathy | The statistical aspects of nuclear reactor fuel element temperature | |
JPS5931489A (ja) | 原子炉の炉心性能計算装置 | |
Adorján et al. | VERONA-plus: extended core-monitoring system for WWER-440 type nuclear power plants | |
Chae | Review of computational methods for space-time reactor kinetics | |
RU2093908C1 (ru) | Способ относительного измерения суммарного состава делящихся изотопов u-235, pu-239, pu-241, в активной зоне водоводяного гетерогенного реактора с многоконтурной схемой теплообмена | |
Johnson et al. | Thermal-hydraulic analysis of the dual-function gamma thermometer |