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Title: Verification of Historical System Transient Simulations for the RHF Research Reactor

Abstract

The RELAP5/Mod 3.3 [1] reactor transient analysis code was used to perform a verification of the RHF reactor system transients previously simulated with the CATHARE Code. The verification included comparisons of temperature, pressure, flows, etc. where direct code comparisons could be made. This work is a precursor to the simulations that will be performed with the RELAP5 code to evaluate the impact of converting the RHF reactor from Highly Enriched Uranium (HEU) to Low Enriched Uranium (LEU) fuel.

Authors:
 [1];  [1];  [1];  [2]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
  2. Institut Laue-Langevin (ILL), Grenoble (France)
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20). Office of Material Management and Minimization (M3)
OSTI Identifier:
1463240
Report Number(s):
ANL/RTR/TM-15/5
143454; TRN: US1901664
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 97 MATHEMATICS AND COMPUTING

Citation Formats

Licht, J. R., Bergeron, A., Dionne, B., and Thomas, F. Verification of Historical System Transient Simulations for the RHF Research Reactor. United States: N. p., 2017. Web. doi:10.2172/1463240.
Licht, J. R., Bergeron, A., Dionne, B., & Thomas, F. Verification of Historical System Transient Simulations for the RHF Research Reactor. United States. doi:10.2172/1463240.
Licht, J. R., Bergeron, A., Dionne, B., and Thomas, F. Fri . "Verification of Historical System Transient Simulations for the RHF Research Reactor". United States. doi:10.2172/1463240. https://www.osti.gov/servlets/purl/1463240.
@article{osti_1463240,
title = {Verification of Historical System Transient Simulations for the RHF Research Reactor},
author = {Licht, J. R. and Bergeron, A. and Dionne, B. and Thomas, F.},
abstractNote = {The RELAP5/Mod 3.3 [1] reactor transient analysis code was used to perform a verification of the RHF reactor system transients previously simulated with the CATHARE Code. The verification included comparisons of temperature, pressure, flows, etc. where direct code comparisons could be made. This work is a precursor to the simulations that will be performed with the RELAP5 code to evaluate the impact of converting the RHF reactor from Highly Enriched Uranium (HEU) to Low Enriched Uranium (LEU) fuel.},
doi = {10.2172/1463240},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {9}
}

Technical Report:

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