34 results on '"Kenichi KURISAKA"'
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2. Development of probabilistic risk assessment methodology of decay heat removal function against combination hazard of low temperature and snow for sodium-cooled fast reactors
3. Development of a probabilistic risk assessment methodology against a combination hazard of strong wind and rainfall for sodium-cooled fast reactors
4. Updating of local blockage frequency in the reactor core of SFR and PRA on consequent severe accident in Monju
5. Development of probabilistic risk assessment methodology against extreme snow for sodium-cooled fast reactor
6. Fundamental Study on Failure Evaluation Method of Integrated Vibration Energy for Component
7. Fundamental safety strategy against severe accidents on prototype sodium-cooled fast reactor
8. Study on Seismic Analysis Method of Fast Reactor Plant with Seismic Isolation System
9. Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling
10. Updating of adventitious fuel pin failure frequency in sodium-cooled fast reactors and probabilistic risk assessment on consequent severe accident in Monju
11. Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors
12. Development of level-1 PSA method applicable to Japan Sodium-cooled Fast Reactor
13. Level 1 PRA for External Vessel Storage Tank in Whole Core Refueling in Advanced Loop-Type Sodium-Cooled Fast Reactor
14. Development of Risk Assessment Methodology of Decay Heat Removal Function Against Natural External Hazards for Sodium-Cooled Fast Reactors: Project Overview and Volcanic PRA Methodology
15. Evaluation of MONJU Core Damage Risk due to Control Rod Function Failure
16. Development of System Based Code (1) Reliability Target Derivation of Structures and Components
17. Development of System Based Code (2) Application of Reliability Target for Configuration of ISI Requirement
18. Assessment of FBR MONJU Accident Management Reliability in Causing Reactor Trips
19. Technological Feasibility of Two-Loop Cooling System in JSFR
20. Study on Minimum Wall Thickness Requirement for Seismic Buckling of Reactor Vessel Based on System Based Code Concept
21. Study on Minimum Wall Thickness Requirement of Reactor Vessel of Fast Reactor for Seismic Buckling by System Based Code
22. Research and Development of Probabilistic Risk Assessment Methodology for Combination Event of Low Temperature and Snow
23. Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor
24. Development of System Based Code: Part 1—Reliability Target Derivation of Structures and Components
25. Development of System Based Code: Part 2—Application of Reliability Target for Configuration of ISI Request
26. Evaluation of Monju Core Damage Risk With Change of AOT Using Probabilistic Method
27. ICONE23-1003 DEVELOPMENT OF RISK ASSESSMENT METHODOLOGY OF DECAY HEAT REMOVAL FUNCTION AGAINST EXTERNAL HAZARDS FOR SODIUM-COOLED FAST REACTORS : (1) PROJECT OVERVIEW AND MARGIN ASSESSMENT METHODOLOGY AGAINST SNOW
28. ICONE23-1112 DEVELOPMENT OF RISK ASSESSMENT METHODOLOGY OF DECAY HEAT REMOVAL FUNCTION AGAINST EXTERNAL HAZARDS FOR SODIUM-COOLED FAST REACTORS : (2) PROBABILISTIC RISK ASSESSMENT METHODOLOGY AGAINST STRONG WIND
29. ATWS Frequency Evaluation of FBR MONJU
30. 528 Study on Seismic Response of Isolated Nuclear Power Plant based on Probabilistic Assessment : 1st Report, Modeling Considering Nonlinearity of Rubber Bearings
31. 529 Study on Seismic Response of Isolated Nuclear Power Plant based on Probabilistic Assessment : 2nd Report, Sensitivity Analysis on Parameter of Isolated Nuclear Power Plant Model
32. ICONE19-43802 PRELIMINARY EVALUATION OF JSFR ACHIEVEMENT LEVEL TO RISK TARGETS
33. J101021 Seismic Response of Isolated Nuclear Power Plant Considering Nonlinearity of Rubber Bearings
34. ICONE11-36388 RISK ANALYSIS OF THE AQUEOUS FAST REACTOR FUEL CYCLE FACILITY IN THE CONCEPTUAL DESIGN STAGE
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