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Title: Applicability of RELAP5 for safety analysis of AP600 and PIUS reactors. [Advanced reactors]

Abstract

An assessment of the applicability of using RELAP5 for performing safety analyses of the AP600 and PIUS advanced reactor concepts is being performed. This ongoing work is part of a larger safety assessment of advanced reactors sponsored by the United States Nuclear Regulatory Commission. RELAP5 models and correlations are being reviewed from the perspective of the new AP600 and PIUS phenomena and features that could be important to reactor safety. The purpose is to identify those areas in which new mathematical models of physical phenomena would be required to be added to RELAP5. In most cases, the AP600 and PIUS designs and systems and the planned and off-normal operations are similar enough to current Pressurized Water Reactors (PWR) that RELAP5 safety analysis applicability is unchanged. However, for AP600 the single most important systemic and phenomenological difference between it and current PWRs is in the close coupling between the reactor system and the containment during postulated Loss of Coolant Accident (LOCA) events. This close coupling may require the addition of some thermal-hydraulic models to RELAP5. And for PIUS, the most important new feature is the thermal density locks. These and other important safety-related features are discussed. This document presents general descriptionsmore » of RELAP5, AP600, and PIUS, describes the new features and phenomena of the reactors, and discusses the code/reactors safety-related issues. 32 refs., 4 figs., 2 tabs.« less

Authors:
;
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Org.:
USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
6207546
Report Number(s):
EGG-M-90390; CONF-9009219-9
ON: DE91018712; TRN: 91-033117
DOE Contract Number:
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: 1990 joint RELAP5 and TRAC-BWR international user seminar, Chicago, IL (United States), 17-21 Sep 1990
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; SAFETY ANALYSIS; AFTER-HEAT REMOVAL; CONTAINMENT; DEPRESSURIZATION; ENGINEERED SAFETY SYSTEMS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PIPES; PUMPS; R CODES; REACTOR COMPONENTS; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR KINETICS; REACTOR SAFETY; REACTOR VESSELS; ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; KINETICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Motloch, C.G., and Modro, S.M. Applicability of RELAP5 for safety analysis of AP600 and PIUS reactors. [Advanced reactors]. United States: N. p., 1990. Web.
Motloch, C.G., & Modro, S.M. Applicability of RELAP5 for safety analysis of AP600 and PIUS reactors. [Advanced reactors]. United States.
Motloch, C.G., and Modro, S.M. Mon . "Applicability of RELAP5 for safety analysis of AP600 and PIUS reactors. [Advanced reactors]". United States. doi:.
@article{osti_6207546,
title = {Applicability of RELAP5 for safety analysis of AP600 and PIUS reactors. [Advanced reactors]},
author = {Motloch, C.G. and Modro, S.M.},
abstractNote = {An assessment of the applicability of using RELAP5 for performing safety analyses of the AP600 and PIUS advanced reactor concepts is being performed. This ongoing work is part of a larger safety assessment of advanced reactors sponsored by the United States Nuclear Regulatory Commission. RELAP5 models and correlations are being reviewed from the perspective of the new AP600 and PIUS phenomena and features that could be important to reactor safety. The purpose is to identify those areas in which new mathematical models of physical phenomena would be required to be added to RELAP5. In most cases, the AP600 and PIUS designs and systems and the planned and off-normal operations are similar enough to current Pressurized Water Reactors (PWR) that RELAP5 safety analysis applicability is unchanged. However, for AP600 the single most important systemic and phenomenological difference between it and current PWRs is in the close coupling between the reactor system and the containment during postulated Loss of Coolant Accident (LOCA) events. This close coupling may require the addition of some thermal-hydraulic models to RELAP5. And for PIUS, the most important new feature is the thermal density locks. These and other important safety-related features are discussed. This document presents general descriptions of RELAP5, AP600, and PIUS, describes the new features and phenomena of the reactors, and discusses the code/reactors safety-related issues. 32 refs., 4 figs., 2 tabs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1990},
month = {Mon Jan 01 00:00:00 EST 1990}
}

Conference:
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