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Title: Posttest analysis of international standard problem 10 using RELAP4/MOD7. [PWR]

RELAP4/MOD7, a best estimate computer code for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This paper evaluates the capability of RELAP4/MOD7 to calculate refill/reflood phenomena. This evaluation uses the data of International Standard Problem 10, which is based on West Germany's KWU PKL refill/reflood experiment K9A. The PKL test facility represents a typical West German four-loop, 1300 MW pressurized water reactor (PWR) in reduced scale while maintaining prototypical volume-to-power ratio. The PKL facility was designed to specifically simulate the refill/reflood phase of a hypothetical loss-of-coolant accident (LOCA).
Authors:
; ; ;
Publication Date:
OSTI Identifier:
6273296
Report Number(s):
CONF-810606-73
ON: DE81026017; TRN: 81-016041
DOE Contract Number:
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
Research Org:
EG and G Idaho, Inc., Idaho Falls (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOSS OF COOLANT; HEAT TRANSFER; HYDRAULICS; PWR TYPE REACTORS; COMPUTER CALCULATIONS; REACTOR SAFETY; TEMPERATURE DISTRIBUTION; ACCIDENTS; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled