Identification and assessment of BWR in-vessel severe accident mitigation strategies Submitted by Fukushima Nucl… on Fri, 12/04/2020 - 10:12 Read more about Identification and assessment of BWR in-vessel severe accident mitigation strategies
BWR owners' group emergency procedure and severe accident guidelines Submitted by Fukushima Nucl… on Fri, 12/04/2020 - 10:12 Read more about BWR owners' group emergency procedure and severe accident guidelines
Cask for 38 fuel assembly BWR Type Provide by Tokyo Electric Power Compay Submitted by Fukushima Nucl… on Fri, 12/04/2020 - 10:12 Read more about Cask for 38 fuel assembly BWR Type Provide by Tokyo Electric Power Compay
BWR用核燃料38体用の輸送容器 Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17 Read more about BWR用核燃料38体用の輸送容器
NRC Japan site team recommendations for improving the September 2011 NISA report to the International Atomic Energy Agency(IAEA) Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17 Read more about NRC Japan site team recommendations for improving the September 2011 NISA report to the International Atomic Energy Agency(IAEA)
Perspectives from the NRC hydrogeology team TASK TRACKER#14 Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17 Read more about Perspectives from the NRC hydrogeology team TASK TRACKER#14
Perspectives from the NRC hydrogeology team JETT#5310 Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17 Read more about Perspectives from the NRC hydrogeology team JETT#5310
Questionnaire to NRC about Fukushima accident Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17 Read more about Questionnaire to NRC about Fukushima accident
The accident at TEPCO's Fukushima Nuclear Power Stations Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17 Read more about The accident at TEPCO's Fukushima Nuclear Power Stations
Assessment of core status of TEPCO's Fukushima daiichi nuclear power plants (47) - validation of the SAMPSON/MCRA code against the CORA-18 experiment Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17 Read more about Assessment of core status of TEPCO's Fukushima daiichi nuclear power plants (47) - validation of the SAMPSON/MCRA code against the CORA-18 experiment