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Title: RELAP5-3D code validation for RBMK phenomena

Abstract

The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a channel inlet pipe rupture test, and a high power, density wave oscillation test. The results showed that RELAP5-3D has the capability to adequately represent these RBMK-related phenomena.

Authors:
Publication Date:
Research Org.:
Idaho National Engineering and Environmental Lab., Idaho Falls, ID (US)
Sponsoring Org.:
USDOE Office of Nonproliferation and National Security (NN) (US)
OSTI Identifier:
752162
Report Number(s):
INEEL/EXT-99-00924
TRN: US0001358
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 1 Sep 1999
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; R CODES; HEAT TRANSFER; HYDRAULICS; REACTOR SAFETY EXPERIMENTS; VALIDATION; LWGR TYPE REACTORS; REACTOR ACCIDENTS; THERMAL-HYDRAULIC; RBMK REACTOR; PARALLEL CHANNEL FLOW; WATER LEVELS; PIPE RUPTURE; HIGH POWER; RELAP5-3D; HIGH DENSITY

Citation Formats

Fisher, J.E. RELAP5-3D code validation for RBMK phenomena. United States: N. p., 1999. Web. doi:10.2172/752162.
Fisher, J.E. RELAP5-3D code validation for RBMK phenomena. United States. doi:10.2172/752162.
Fisher, J.E. Wed . "RELAP5-3D code validation for RBMK phenomena". United States. doi:10.2172/752162. https://www.osti.gov/servlets/purl/752162.
@article{osti_752162,
title = {RELAP5-3D code validation for RBMK phenomena},
author = {Fisher, J.E.},
abstractNote = {The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a channel inlet pipe rupture test, and a high power, density wave oscillation test. The results showed that RELAP5-3D has the capability to adequately represent these RBMK-related phenomena.},
doi = {10.2172/752162},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {9}
}