RU2013113711A - УСТРОЙСТВО ДЛЯ ИЗМЕРЕНИЯ ОСТАТОЧНОЙ МОЩНОСТИ ОТРАБОТАВШЕЙ ТОПЛИВНОЙ СБОРКИ, ПРЕДНАЗНАЧЕННОЕ ДЛЯ ВЫГРУЗКИ ИЗ РЕАКТОРА С ОХЛАЖДЕНИЕМ, ЖИДКИМ МЕТАЛЛОМ, НАПРИМЕР, РЕАКТОРА БН-Na (RNR-Na/SFR) - Google Patents
УСТРОЙСТВО ДЛЯ ИЗМЕРЕНИЯ ОСТАТОЧНОЙ МОЩНОСТИ ОТРАБОТАВШЕЙ ТОПЛИВНОЙ СБОРКИ, ПРЕДНАЗНАЧЕННОЕ ДЛЯ ВЫГРУЗКИ ИЗ РЕАКТОРА С ОХЛАЖДЕНИЕМ, ЖИДКИМ МЕТАЛЛОМ, НАПРИМЕР, РЕАКТОРА БН-Na (RNR-Na/SFR) Download PDFInfo
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- RU2013113711A RU2013113711A RU2013113711/07A RU2013113711A RU2013113711A RU 2013113711 A RU2013113711 A RU 2013113711A RU 2013113711/07 A RU2013113711/07 A RU 2013113711/07A RU 2013113711 A RU2013113711 A RU 2013113711A RU 2013113711 A RU2013113711 A RU 2013113711A
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- container
- assembly
- measuring device
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- support
- Prior art date
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Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
- G01K17/00—Measuring quantity of heat
- G01K17/06—Measuring quantity of heat conveyed by flowing media, e.g. in heating systems e.g. the quantity of heat in a transporting medium, delivered to or consumed in an expenditure device
- G01K17/08—Measuring quantity of heat conveyed by flowing media, e.g. in heating systems e.g. the quantity of heat in a transporting medium, delivered to or consumed in an expenditure device based upon measurement of temperature difference or of a temperature
- G01K17/10—Measuring quantity of heat conveyed by flowing media, e.g. in heating systems e.g. the quantity of heat in a transporting medium, delivered to or consumed in an expenditure device based upon measurement of temperature difference or of a temperature between an inlet and an outlet point, combined with measurement of rate of flow of the medium if such, by integration during a certain time-interval
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
- G21C17/063—Burn-up control
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
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- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- General Physics & Mathematics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1253021A FR2988837A1 (fr) | 2012-04-02 | 2012-04-02 | Dispositif de mesure de la puissance residuelle d'un assemblage combustible use, destine a etre decharge d'un reacteur refroidi au metal liquide, tel qu'un reacteur rnr-na ou sfr. |
FR1253021 | 2012-04-02 |
Publications (1)
Publication Number | Publication Date |
---|---|
RU2013113711A true RU2013113711A (ru) | 2014-10-10 |
Family
ID=46551730
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
RU2013113711/07A RU2013113711A (ru) | 2012-04-02 | 2013-03-28 | УСТРОЙСТВО ДЛЯ ИЗМЕРЕНИЯ ОСТАТОЧНОЙ МОЩНОСТИ ОТРАБОТАВШЕЙ ТОПЛИВНОЙ СБОРКИ, ПРЕДНАЗНАЧЕННОЕ ДЛЯ ВЫГРУЗКИ ИЗ РЕАКТОРА С ОХЛАЖДЕНИЕМ, ЖИДКИМ МЕТАЛЛОМ, НАПРИМЕР, РЕАКТОРА БН-Na (RNR-Na/SFR) |
Country Status (5)
Country | Link |
---|---|
JP (1) | JP2013213823A (ja) |
KR (1) | KR20130112008A (ja) |
CN (1) | CN103366842A (ja) |
FR (1) | FR2988837A1 (ja) |
RU (1) | RU2013113711A (ja) |
Families Citing this family (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR3019931B1 (fr) * | 2014-04-11 | 2016-05-13 | Commissariat Energie Atomique | Unite de chargement / dechargement d'assemblages combustibles d'un reacteur refroidi au metalliquide, tel qu'un reacteur rnr-na ou sfr, integrant un dispositif de mesure de la puissance residuelle |
FR3019930A1 (fr) * | 2014-04-11 | 2015-10-16 | Commissariat Energie Atomique | Dispositif de mesure de la puissance residuelle d'un assemblage combustible use, destine a etre decharge d'un reacteur refroidi au metal liquide, tel qu'un reacteur rnr-na ou sfr |
FR3042901B1 (fr) * | 2015-10-23 | 2017-12-15 | Commissariat Energie Atomique | Dispositif de declenchement et d'insertion d'elements absorbants et/ou mitigateurs d'un reacteur nucleaire mettant en œuvre des elements flexibles et assemblage de combustible nucleaire comportant un tel dispositif |
BE1023950B1 (fr) * | 2016-03-15 | 2017-09-20 | Centre De Recherches Metallurgiques Asbl Centrum Voor Res In De Metallurgie Vzw | Mesure de température en continu dans un métal liquide |
CN107192462A (zh) * | 2017-06-23 | 2017-09-22 | 西安交通大学 | 一种钠冷快堆组件试验件的多维度扫描测温装置及方法 |
CN107622803A (zh) * | 2017-10-12 | 2018-01-23 | 中国科学技术大学 | 一种可有效提升池式铅冷快堆安全性的冷池流道 |
CN108053903B (zh) * | 2017-12-21 | 2024-05-10 | 中国原子能科学研究院 | 一种高温钠中裂变产物滞留因子测量装置 |
CN108897950B (zh) * | 2018-06-28 | 2020-05-22 | 西安交通大学 | 一种堆芯熔化收集器的优化设计方法 |
FR3125627B1 (fr) * | 2021-07-22 | 2023-07-28 | Commissariat Energie Atomique | Système de détermination d’une puissance générée par un assemblage, réacteur nucléaire et procédé de détermination de la puissance |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3906892A1 (de) * | 1989-03-03 | 1990-09-06 | Wiederaufarbeitung Von Kernbre | Verfahren und vorrichtung zur messung von nachzerfallswaerme abgebenden stoffen |
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2012
- 2012-04-02 FR FR1253021A patent/FR2988837A1/fr active Pending
-
2013
- 2013-03-28 RU RU2013113711/07A patent/RU2013113711A/ru not_active Application Discontinuation
- 2013-03-29 JP JP2013086072A patent/JP2013213823A/ja active Pending
- 2013-04-02 CN CN2013101133171A patent/CN103366842A/zh active Pending
- 2013-04-02 KR KR1020130035738A patent/KR20130112008A/ko not_active Application Discontinuation
Also Published As
Publication number | Publication date |
---|---|
KR20130112008A (ko) | 2013-10-11 |
JP2013213823A (ja) | 2013-10-17 |
CN103366842A (zh) | 2013-10-23 |
FR2988837A1 (fr) | 2013-10-04 |
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Legal Events
Date | Code | Title | Description |
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FA93 | Acknowledgement of application withdrawn (no request for examination) |
Effective date: 20160329 |