JPH04236B2 - - Google Patents

Info

Publication number
JPH04236B2
JPH04236B2 JP58209682A JP20968283A JPH04236B2 JP H04236 B2 JPH04236 B2 JP H04236B2 JP 58209682 A JP58209682 A JP 58209682A JP 20968283 A JP20968283 A JP 20968283A JP H04236 B2 JPH04236 B2 JP H04236B2
Authority
JP
Japan
Prior art keywords
accident
reactor
time
scale
internal state
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 - Lifetime
Application number
JP58209682A
Other languages
English (en)
Japanese (ja)
Other versions
JPS60100795A (ja
Inventor
Hiroari Fukunishi
Koji Ooga
Masao Kawai
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 JP58209682A priority Critical patent/JPS60100795A/ja
Publication of JPS60100795A publication Critical patent/JPS60100795A/ja
Publication of JPH04236B2 publication Critical patent/JPH04236B2/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)
JP58209682A 1983-11-08 1983-11-08 原子炉の事故時炉内状態予測方法および装置 Granted JPS60100795A (ja)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58209682A JPS60100795A (ja) 1983-11-08 1983-11-08 原子炉の事故時炉内状態予測方法および装置

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58209682A JPS60100795A (ja) 1983-11-08 1983-11-08 原子炉の事故時炉内状態予測方法および装置

Publications (2)

Publication Number Publication Date
JPS60100795A JPS60100795A (ja) 1985-06-04
JPH04236B2 true JPH04236B2 (https=) 1992-01-06

Family

ID=16576871

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58209682A Granted JPS60100795A (ja) 1983-11-08 1983-11-08 原子炉の事故時炉内状態予測方法および装置

Country Status (1)

Country Link
JP (1) JPS60100795A (https=)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP3394817B2 (ja) * 1994-06-20 2003-04-07 株式会社東芝 プラント診断装置
JP6659225B2 (ja) * 2015-03-12 2020-03-04 株式会社東芝 原子炉圧力容器内水位推定装置および原子炉圧力容器内水位推定方法
JP6964423B2 (ja) * 2017-03-27 2021-11-10 三菱重工業株式会社 プラント運転シミュレーション装置、プラント運転シミュレーション方法及びプログラム
JP2023179090A (ja) * 2022-06-07 2023-12-19 三菱重工業株式会社 炉心計算方法、炉心計算装置及びプログラム

Also Published As

Publication number Publication date
JPS60100795A (ja) 1985-06-04

Similar Documents

Publication Publication Date Title
JPH0371203A (ja) プラント・オペレーティング・システム
EP3896703A1 (en) Computer-based simulation methods for boiling water reactors (bwr)
JPH04236B2 (https=)
Grahn et al. Modelling of complex boron dilution transients in PWRs—Validation of CFD simulation with ANSYS CFX against the ROCOM E2. 3 experiment
Kwon et al. Compact nuclear simulator and its upgrade plan
Schaffrath et al. Validation of the CFD code fluent by post-test calculation of a density-driven ROCOM experiment
Baghban et al. Simulating and evaluating the pressurizer dynamic behavior in various sizes
JPH0413679B2 (https=)
Blinkov et al. Investigation on the interphase drag and wall friction in vertically oriented upward and downward two-phase flows under accident conditions in light water reactors
JPS6212878B2 (https=)
Bajs et al. Development of the qualified plant nodalization for safety and operational transient analysis
JPS6151208A (ja) 予測シミユレ−タ
Alawad Thermal–hydraulic phenomenology analysis and RELAP5/MOD3. 3 code assessment for ATLAS 1% upper head SBLOCA test
Liu et al. Improvement of ATHLET modelling capability for asymmetric natural circulation phenomenon using uncertainty and sensitivity measures
Zarghami et al. The dynamic modeling of the pressurizer surge tank transients in light water reactor nuclear power plants
JPS59126289A (ja) 原子炉の破断検知装置
Hwang Method of estimating break size in piping loop systems
JPS61112214A (ja) 予測ガイド出力装置
Tiberg Simulation of IB-LOCA in TRACE: A semi-blind study of numerical simulations compared to the PKL test facility
JPH04265899A (ja) 原子炉シミュレータ
Glaeser Validation and uncertainty analysis of the Athlet thermal-hydraulic computer code
Cartmill Thermal-hydraulic response of the semiscale Mod-1 system: isothermal test series
Youssefnia An investigative approach to study the RETRAN modeling concepts in the analysis of a safety valve discharge transient
Wachs A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility
Osadchaya et al. The SAM software system for modeling severe accidents at nuclear power plants equipped with VVER reactors on full-scale and analytic training simulators