Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research
Publisher:
ISBN:
Category : Containment
Languages : en
Pages : 316
Book Description
Severe Accident Risks: Final summary report
Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research
Publisher:
ISBN:
Category : Containment
Languages : en
Pages : 316
Book Description
Publisher:
ISBN:
Category : Containment
Languages : en
Pages : 316
Book Description
Severe Accident Risks: Final summary report
Severe Accident Risks: Final summary report
Severe accident risks : an assessment for five U.S. nuclear power plants : final summary report : volume 1
Severe Accident Risks: Appendices D and E, final report
Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 102
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 102
Book Description
Severe Accident Risks: Appendices A, B, and C, final report
Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 324
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 324
Book Description
Severe accident risks : an assessment for five U.S. nuclear power plants : summary report : second draft for peer review
Evaluation of Severe Accident Risks, Peach Bottom, Unit 2
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 691
Book Description
In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe accidents at commercial nuclear power plants in the US reported NUREG-1150, the Severe Accident Risk Reduction Program (SARRP) has completed a revised calculation of the risk to the general public from severe accidents at the Peach Bottom Atomic Power Station, Unit 2. This power plant, located in southeastern Pennsylvania, is operated by the Philadelphia Electric Company. The emphasis in this risk analysis was not on determining a so-called'' point estimate of risk. Rather, it was to determine the distribution of risk, and to discover the uncertainties that account for the breadth of this distribution. Off-site risk initiated by events both internal and external to the power station were assessed. 39 refs., 174 figs., 133 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages : 691
Book Description
In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe accidents at commercial nuclear power plants in the US reported NUREG-1150, the Severe Accident Risk Reduction Program (SARRP) has completed a revised calculation of the risk to the general public from severe accidents at the Peach Bottom Atomic Power Station, Unit 2. This power plant, located in southeastern Pennsylvania, is operated by the Philadelphia Electric Company. The emphasis in this risk analysis was not on determining a so-called'' point estimate of risk. Rather, it was to determine the distribution of risk, and to discover the uncertainties that account for the breadth of this distribution. Off-site risk initiated by events both internal and external to the power station were assessed. 39 refs., 174 figs., 133 tabs.
Evaluation of Severe Accident Risks: Zion, Unit 1
Evaluation of Severe Accident Risks
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 441
Book Description
This report records part of the vast amount of information received during the expert judgment elicitation process that took place in support of the NUREG-1150 effort sponsored by the U.S. Nuclear Regulatory Commission. The results of the Containment Loads and Molten Core/Containment Interaction Expert Panel Elicitation are presented in this part of Volume 2 of NUREG/CR-4551. The Containment Loads Expert Panel considered seven issues: (1) hydrogen phenomena at Grand Gulf; (2) hydrogen burn at vessel breach at Sequoyah; (3) BWR reactor building failure due to hydrogen; (4) Grand Gulf containment loads at vessel breach; (5) pressure increment in the Sequoyah containment at vessel breach; (6) loads at vessel breach: Surry; and (7) pressure increment in the Zion containment at vessel breach. The report begins with a brief discussion of the methods used to elicit the information from the experts. The information for each issue is then presented in five sections: (1) a brief definition of the issue, (2) a brief summary of the technical rationale supporting the distributions developed by each of the experts, (3) a brief description of the operations that the project staff performed on the raw elicitation results in order to aggregate the distributions, (4) the aggregated distributions, and (5) the individual expert elicitation summaries. The Molten Core/Containment Interaction Panel considered three issues. The results of the following two of these issues are presented in this document: (1) Peach Bottom drywell shell meltthrough; and (2) Grand Gulf pedestal erosion. 89 figs., 154 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages : 441
Book Description
This report records part of the vast amount of information received during the expert judgment elicitation process that took place in support of the NUREG-1150 effort sponsored by the U.S. Nuclear Regulatory Commission. The results of the Containment Loads and Molten Core/Containment Interaction Expert Panel Elicitation are presented in this part of Volume 2 of NUREG/CR-4551. The Containment Loads Expert Panel considered seven issues: (1) hydrogen phenomena at Grand Gulf; (2) hydrogen burn at vessel breach at Sequoyah; (3) BWR reactor building failure due to hydrogen; (4) Grand Gulf containment loads at vessel breach; (5) pressure increment in the Sequoyah containment at vessel breach; (6) loads at vessel breach: Surry; and (7) pressure increment in the Zion containment at vessel breach. The report begins with a brief discussion of the methods used to elicit the information from the experts. The information for each issue is then presented in five sections: (1) a brief definition of the issue, (2) a brief summary of the technical rationale supporting the distributions developed by each of the experts, (3) a brief description of the operations that the project staff performed on the raw elicitation results in order to aggregate the distributions, (4) the aggregated distributions, and (5) the individual expert elicitation summaries. The Molten Core/Containment Interaction Panel considered three issues. The results of the following two of these issues are presented in this document: (1) Peach Bottom drywell shell meltthrough; and (2) Grand Gulf pedestal erosion. 89 figs., 154 tabs.