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Title: High Flux Isotope Reactor system RELAP5 input model

Abstract

A thermal-hydraulic computational model of the High Flux Isotope Reactor (HFIR) has been developed using the RELAP5 program. The purpose of the model is to provide a state-of-the art thermal-hydraulic simulation tool for analyzing selected hypothetical accident scenarios for a revised HFIR Safety Analysis Report (SAR). The model includes (1) a detailed representation of the reactor core and other vessel components, (2) three heat exchanger/pump cells, (3) pressurizing pumps and letdown valves, and (4) secondary coolant system (with less detail than the primary system). Data from HFIR operation, component tests, tests in facility mockups and the HFIR, HFIR specific experiments, and other pertinent experiments performed independent of HFIR were used to construct the model and validate it to the extent permitted by the data. The detailed version of the model has been used to simulate loss-of-coolant accidents (LOCAs), while the abbreviated version has been developed for the operational transients that allow use of a less detailed nodalization. Analysis of station blackout with core long-term decay heat removal via natural convection has been performed using the core and vessel portions of the detailed model.

Authors:
;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10129831
Report Number(s):
ORNL/TM-11647
ON: DE93007789
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Jan 1993
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; HFIR REACTOR; REACTOR ACCIDENTS; R CODES; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; HEAT EXCHANGERS; FUEL ELEMENTS; THERMAL CONDUCTIVITY; SAFETY ANALYSIS; 220900; 220600; REACTOR SAFETY; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS

Citation Formats

Morris, D G, and Wendel, M W. High Flux Isotope Reactor system RELAP5 input model. United States: N. p., 1993. Web. doi:10.2172/10129831.
Morris, D G, & Wendel, M W. High Flux Isotope Reactor system RELAP5 input model. United States. https://doi.org/10.2172/10129831
Morris, D G, and Wendel, M W. 1993. "High Flux Isotope Reactor system RELAP5 input model". United States. https://doi.org/10.2172/10129831. https://www.osti.gov/servlets/purl/10129831.
@article{osti_10129831,
title = {High Flux Isotope Reactor system RELAP5 input model},
author = {Morris, D G and Wendel, M W},
abstractNote = {A thermal-hydraulic computational model of the High Flux Isotope Reactor (HFIR) has been developed using the RELAP5 program. The purpose of the model is to provide a state-of-the art thermal-hydraulic simulation tool for analyzing selected hypothetical accident scenarios for a revised HFIR Safety Analysis Report (SAR). The model includes (1) a detailed representation of the reactor core and other vessel components, (2) three heat exchanger/pump cells, (3) pressurizing pumps and letdown valves, and (4) secondary coolant system (with less detail than the primary system). Data from HFIR operation, component tests, tests in facility mockups and the HFIR, HFIR specific experiments, and other pertinent experiments performed independent of HFIR were used to construct the model and validate it to the extent permitted by the data. The detailed version of the model has been used to simulate loss-of-coolant accidents (LOCAs), while the abbreviated version has been developed for the operational transients that allow use of a less detailed nodalization. Analysis of station blackout with core long-term decay heat removal via natural convection has been performed using the core and vessel portions of the detailed model.},
doi = {10.2172/10129831},
url = {https://www.osti.gov/biblio/10129831}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1993},
month = {Fri Jan 01 00:00:00 EST 1993}
}