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Title: Identification and characterization of passive safety system and inherent safety feature building blocks for advanced light-water reactors

Oak Ridge National Laboratory (ORNL) is investigating passive and inherent safety options for Advanced Light-Water Reactors (ALWRs). A major activity in 1989 includes identification and characterization of passive safety system and inherent safety feature building blocks, both existing and proposed, for ALWRs. Preliminary results of this work are reported herein. This activity is part of a larger effort by the US Department of Energy, reactor vendors, utilities, and others in the United States to develop improved LWRs. The Advanced Boiling Water Reactor (ABWR) program and the Advanced Pressurized Water Reactor (APWR) program have as goals improved, commercially available LWRs in the early 1990s. The Advanced Simplified Boiling Water Reactor (ASBWR) program and the AP-600 program are developing more advanced reactors with increased use of passive safety systems. It is planned that these reactors will become commercially available in the mid 1990s. The ORNL program is an exploratory research program for LWRs beyond the year 2000. Desired long-term goals for such reactors include: (1) use of only passive and inherent safety, (2) foolproof against operator errors, (3) malevolence resistance against internal sabotage and external assault and (4) walkaway safety. The acronym ''PRIME'' (Passive safety, Resilient operation, Inherent safety, Malevolence resistance, andmore » Extended (walkaway) safety) is used to summarize these desired characteristics. Existing passive and inherent safety options are discussed in this document.« less
Authors:
Publication Date:
OSTI Identifier:
6298465
Report Number(s):
CONF-890395-1
ON: DE89009111
DOE Contract Number:
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: International Atomic Energy Agency technical committee meeting on passive safety features in current and future water-cooled reactors, Moscow, USSR, 21 Mar 1989; Other Information: Portions of this document are illegible in microfiche products
Research Org:
Oak Ridge National Lab., TN (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR SAFETY; PWR TYPE REACTORS; CONTAINMENT; CONTROL ELEMENTS; DESIGN; ENGINEERED SAFETY SYSTEMS; HEAT TRANSFER; HYDRAULICS; REACTOR COMPONENTS; SHIELDING; SYSTEMS ANALYSIS; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled