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Realistic Simulation of Severe Accidents in BWRs

Realistic Simulation of Severe Accidents in BWRs PDF Author: Sherrell R. Greene
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 220

Book Description


Realistic Simulation of Severe Accidents in BWRs

Realistic Simulation of Severe Accidents in BWRs PDF Author: Sherrell R. Greene
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 220

Book Description


DEMONSTRATION OF FULLY COUPLED SIMPLIFIED EXTENDED STATION BLACK-OUT ACCIDENT SIMULATION WITH RELAP-7

DEMONSTRATION OF FULLY COUPLED SIMPLIFIED EXTENDED STATION BLACK-OUT ACCIDENT SIMULATION WITH RELAP-7 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at the Idaho National Laboratory (INL). The RELAP-7 code develop-ment effort started in October of 2011 and by the end of the second development year, a number of physical components with simplified two phase flow capability have been de-veloped to support the simplified boiling water reactor (BWR) extended station blackout (SBO) analyses. The demonstration case includes the major components for the primary system of a BWR, as well as the safety system components for the safety relief valve (SRV), the reactor core isolation cooling (RCIC) system, and the wet well. Three scenar-ios for the SBO simulations have been considered. Since RELAP-7 is not a severe acci-dent analysis code, the simulation stops when fuel clad temperature reaches damage point. Scenario I represents an extreme station blackout accident without any external cooling and cooling water injection. The system pressure is controlled by automatically releasing steam through SRVs. Scenario II includes the RCIC system but without SRV. The RCIC system is fully coupled with the reactor primary system and all the major components are dynamically simulated. The third scenario includes both the RCIC system and the SRV to provide a more realistic simulation. This paper will describe the major models and dis-cuss the results for the three scenarios. The RELAP-7 simulations for the three simplified SBO scenarios show the importance of dynamically simulating the SRVs, the RCIC sys-tem, and the wet well system to the reactor safety during extended SBO accidents.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 780

Book Description


Fission Product Processes In Reactor Accidents

Fission Product Processes In Reactor Accidents PDF Author: J. T. Rogers
Publisher: CRC Press
ISBN: 1000107310
Category : Science
Languages : en
Pages : 883

Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

The Modeling and Analysis of BWR Severe Accidents

The Modeling and Analysis of BWR Severe Accidents PDF Author: Seok H. Kim
Publisher:
ISBN:
Category :
Languages : en
Pages : 301

Book Description


Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 518

Book Description


Key Parameters for Operator Diagnosis of BWR Plant Condition During a Severe Accident

Key Parameters for Operator Diagnosis of BWR Plant Condition During a Severe Accident PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The objective of this research is to examine the key information needed from nuclear power plant instrumentation to guide severe accident management and mitigation for boiling water reactor (BWR) designs (specifically, a BWR/4-Mark I), estimate environmental conditions that the instrumentation will experience during a severe accident, and identify potential gaps in existing instrumentation that may require further research and development. This report notes the key parameters that instrumentation needs to measure to help operators respond to severe accidents. A follow-up report will assess severe accident environmental conditions as estimated by severe accident simulation model analysis for a specific US BWR/4-Mark I plant for those instrumentation systems considered most important for accident management purposes.

Monthly Catalog of United States Government Publications

Monthly Catalog of United States Government Publications PDF Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages :

Book Description


Monthly Catalogue, United States Public Documents

Monthly Catalogue, United States Public Documents PDF Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1140

Book Description


Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 818

Book Description