JPS6329240B2 - - Google Patents

Info

Publication number
JPS6329240B2
JPS6329240B2 JP55087898A JP8789880A JPS6329240B2 JP S6329240 B2 JPS6329240 B2 JP S6329240B2 JP 55087898 A JP55087898 A JP 55087898A JP 8789880 A JP8789880 A JP 8789880A JP S6329240 B2 JPS6329240 B2 JP S6329240B2
Authority
JP
Japan
Prior art keywords
accident
reactor
pressure vessel
containment vessel
reactor pressure
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.)
Expired
Application number
JP55087898A
Other languages
English (en)
Japanese (ja)
Other versions
JPS5713391A (en
Inventor
Masaki Matsumoto
Ryozo Tsuruoka
Tadakazu Nakayama
Tetsuo Horiuchi
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP8789880A priority Critical patent/JPS5713391A/ja
Publication of JPS5713391A publication Critical patent/JPS5713391A/ja
Publication of JPS6329240B2 publication Critical patent/JPS6329240B2/ja
Granted legal-status Critical Current

Links

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)
JP8789880A 1980-06-30 1980-06-30 Device for forecasting core state at accident Granted JPS5713391A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP8789880A JPS5713391A (en) 1980-06-30 1980-06-30 Device for forecasting core state at accident

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP8789880A JPS5713391A (en) 1980-06-30 1980-06-30 Device for forecasting core state at accident

Publications (2)

Publication Number Publication Date
JPS5713391A JPS5713391A (en) 1982-01-23
JPS6329240B2 true JPS6329240B2 (enrdf_load_stackoverflow) 1988-06-13

Family

ID=13927706

Family Applications (1)

Application Number Title Priority Date Filing Date
JP8789880A Granted JPS5713391A (en) 1980-06-30 1980-06-30 Device for forecasting core state at accident

Country Status (1)

Country Link
JP (1) JPS5713391A (enrdf_load_stackoverflow)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2858208B2 (ja) * 1994-04-20 1999-02-17 本田技研工業株式会社 シリンダブロック

Also Published As

Publication number Publication date
JPS5713391A (en) 1982-01-23

Similar Documents

Publication Publication Date Title
US4764335A (en) Method and apparatus for diagnosing breached fuel elements
US4495142A (en) Monitoring system for monitoring state of nuclear reactor core
US4415524A (en) Apparatus for and method of monitoring for breached fuel elements
JPS6329240B2 (enrdf_load_stackoverflow)
Badgley et al. Power-spectral-density measurements in a subcritical nuclear reactor
Allemann et al. EXPERIMENTAL HIGH ENTHALPY WATER BLOWDOWN FROM A SIMPLE VESSEL THROUGH A BOTTOM OUTLET.
Wenger et al. On the origin of the discrepancies between theory and experiment in the COVA series
Antonopoulos-Domis et al. Moderator temperature coefficient of reactivity in Pressurized Water Reactors: theoretical investigation and numerical simulations
Spiegler COMPARISON OF CALCULATED AND MEASURED GAMMA-RAY DOSE RATES AND NEUTRON FLUX DISTRIBUTIONS IN THE SRE INSTRUMENT THIMBLES
JPS6337913B2 (enrdf_load_stackoverflow)
Breazeale The New Bulk Shielding Facility at Oak Ridge National Laboratory
JPH04115193A (ja) 核燃料集合体の平均燃焼度測定装置
RU2302676C1 (ru) Способ определения эффективной интенсивности источника нейтронов заглушенного ядерного реактора
JPH0219919B2 (enrdf_load_stackoverflow)
SU602045A1 (ru) Устройство дл определени концентрации поглащающего нейтроны вещества
RU2179757C2 (ru) Устройство для контроля за оперативным запасом реактивности на стержнях суз ядерного реактора
JPS58150836A (ja) ナトリウム漏洩規模判定方法
JPH02110399A (ja) 原子炉自動起動装置
Bennett et al. Initial fuel load and criticality, zero power and characterization testing
JPH05134079A (ja) 原子炉出力分布監視装置
SU1394999A1 (ru) Устройство дл диагностики системы газового управлени плотностью нейтронного потока
Braid et al. Operation of cover-gas system during SLSF tests
Banerjee et al. 1.2 Fundamental Studies on Heavy Water Reactor Thermalhydraulics
Morfitt Minimum critical mass and uniform thermal neutron core flux in an experimental reactor
JPS63128290A (ja) 核燃料設備の未臨界度モニタ−装置