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USNRC severe core damage assessment program

Abstract

The accident at the Three Mile Island nuclear power station has significantly altered the perception of the importance of beyond-design-basis accidents in licensing and safety reviews of light-water reactors in the USA. Increased consideration will be given by the United States Nuclear Regulatory Commission to low-probability, high-risk core melt accidents in future licensing proceedings. To this end, the USNRC is mounting experimental and analytic methods development programs to provide the technical basis for future LWR design and licensing criteria related to class-9 accidents. The scope, objectives, and content of five major new programs addressing safety and licensing issues for beyond-design-basis accidents are reviewed and the rationale and logic for formulation of the programs is discussed.
Authors:
Hanson, J E; [1]  Johnston, W V; Kelber, C N [2] 
  1. EG and G Idaho, Inc., Idaho Falls (USA)
  2. Nuclear Regulatory Commission, Washington, DC (USA)
Publication Date:
Jan 01, 1981
Product Type:
Conference
Report Number:
STI/PUB-566(Vol.3); CONF-801056-(Vol.3); IAEA-CN-39/105
Reference Number:
AIX-13-680623; EDB-82-163543
Resource Relation:
Conference: International conference on current nuclear power plant safety issues, Stockholm, Sweden, 26 Oct 1980; Related Information: In: Current nuclear power plant safety issues. Proceedings of an international conference organized by the IAEA and held in Stockholm, Sweden, 20-24 October 1980.
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR CORE DISRUPTION; PWR TYPE REACTORS; SAFETY STANDARDS; CONTAINMENT; DESIGN BASIS ACCIDENTS; FUEL ELEMENT FAILURE; HYDRAULICS; PLANNING; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; RESEARCH PROGRAMS; THERMODYNAMICS; TRANSIENTS; US NRC; ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; FLUID MECHANICS; MECHANICS; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; STANDARDS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
OSTI ID:
8436119
Country of Origin:
IAEA
Language:
English
Submitting Site:
INIS
Size:
Pages: 347-362
Announcement Date:
Mar 15, 2013

Citation Formats

Hanson, J E, Johnston, W V, and Kelber, C N. USNRC severe core damage assessment program. IAEA: N. p., 1981. Web.
Hanson, J E, Johnston, W V, & Kelber, C N. USNRC severe core damage assessment program. IAEA.
Hanson, J E, Johnston, W V, and Kelber, C N. 1981. "USNRC severe core damage assessment program." IAEA.
@misc{etde_8436119,
title = {USNRC severe core damage assessment program}
author = {Hanson, J E, Johnston, W V, and Kelber, C N}
abstractNote = {The accident at the Three Mile Island nuclear power station has significantly altered the perception of the importance of beyond-design-basis accidents in licensing and safety reviews of light-water reactors in the USA. Increased consideration will be given by the United States Nuclear Regulatory Commission to low-probability, high-risk core melt accidents in future licensing proceedings. To this end, the USNRC is mounting experimental and analytic methods development programs to provide the technical basis for future LWR design and licensing criteria related to class-9 accidents. The scope, objectives, and content of five major new programs addressing safety and licensing issues for beyond-design-basis accidents are reviewed and the rationale and logic for formulation of the programs is discussed.}
place = {IAEA}
year = {1981}
month = {Jan}
}