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Title: Applications of Monte Carlo methods for the analysis of MHTGR case of the PROTEUS benchmark

Abstract

Monte Carlo methods, as implemented in the MCNP code, have been used to analyze the neutronics characteristics of benchmarks related to Modular High Temperature Gas-Cooled Reactors. The benchmarks are idealized versions of the Japanes (VHTRC) and Swiss (PROTEUS) facilities and an actual configurations of the PROTEUS Configuration I experiment. The purpose of the unit cell benchmarks is to compare multiplication constants, critical bucklings, migration lengths, reaction rates and spectral indices. The purpose of the full reactors benchmarks is to compare multiplication constants, reaction rates, spectral indices, neutron balances, reaction rates profiles, temperature coefficients of reactivity and effective delayed neutron fractions. All of these parameters can be calculated by MCNP, which can provide a very detailed model of the geometry of the configurations, from fuel particles to entire fuel assemblies, using at the same time a continuous energy model. These characteristics make MCNP a very useful tool to analyze these MHTGR benchmarks. We have used the MCNP latest version, 4.x, eld = 01/12/93 with an ENDF/B-V cross section library. This library does not yet contain temperature dependent resonance materials, so all calculations correspond to room temperature, T = 300{degree}K. Two separate reports were made -- one for the VHTRC, the othermore » for the PROTEUS benchmark.« less

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10143282
Report Number(s):
ORNL/TM-12711
ON: DE94010153
DOE Contract Number:
AC05-84OR21400
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Apr 1994
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; HTGR TYPE REACTORS; REACTOR KINETICS; BENCHMARKS; MONTE CARLO METHOD; COATED FUEL PARTICLES; CROSS SECTIONS; M CODES; REACTIVITY; COMPUTER CALCULATIONS; 210300; 220100; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED; THEORY AND CALCULATION

Citation Formats

Difilippo, F.C. Applications of Monte Carlo methods for the analysis of MHTGR case of the PROTEUS benchmark. United States: N. p., 1994. Web. doi:10.2172/10143282.
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Difilippo, F.C. Applications of Monte Carlo methods for the analysis of MHTGR case of the PROTEUS benchmark. United States. doi:10.2172/10143282.
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Difilippo, F.C. Fri . "Applications of Monte Carlo methods for the analysis of MHTGR case of the PROTEUS benchmark". United States. doi:10.2172/10143282. https://www.osti.gov/servlets/purl/10143282.
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@article{osti_10143282,
title = {Applications of Monte Carlo methods for the analysis of MHTGR case of the PROTEUS benchmark},
author = {Difilippo, F.C.},
abstractNote = {Monte Carlo methods, as implemented in the MCNP code, have been used to analyze the neutronics characteristics of benchmarks related to Modular High Temperature Gas-Cooled Reactors. The benchmarks are idealized versions of the Japanes (VHTRC) and Swiss (PROTEUS) facilities and an actual configurations of the PROTEUS Configuration I experiment. The purpose of the unit cell benchmarks is to compare multiplication constants, critical bucklings, migration lengths, reaction rates and spectral indices. The purpose of the full reactors benchmarks is to compare multiplication constants, reaction rates, spectral indices, neutron balances, reaction rates profiles, temperature coefficients of reactivity and effective delayed neutron fractions. All of these parameters can be calculated by MCNP, which can provide a very detailed model of the geometry of the configurations, from fuel particles to entire fuel assemblies, using at the same time a continuous energy model. These characteristics make MCNP a very useful tool to analyze these MHTGR benchmarks. We have used the MCNP latest version, 4.x, eld = 01/12/93 with an ENDF/B-V cross section library. This library does not yet contain temperature dependent resonance materials, so all calculations correspond to room temperature, T = 300{degree}K. Two separate reports were made -- one for the VHTRC, the other for the PROTEUS benchmark.},
doi = {10.2172/10143282},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Apr 01 00:00:00 EST 1994},
month = {Fri Apr 01 00:00:00 EST 1994}
}
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Technical Report:
View Technical Report (3.37 MB)
DOI:  10.2172/10143282
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    The National Nuclear Data Center is continuing its program to improve the nuclear data base used as input for commercial reactor analysis and design. In the most recent phase of this project the Monte Carlo program SAM-CE, developed by the Mathematical Applications Group, Inc. (MAGI), was made operational at BNL. This program was implemented on the BNL-CDC-7600 Computer, and also on the PDP-10 in-house computer. The NNDC made operational and developed techniques for processing ENDF/B-V cross sections for SAM-CE. A limited ENDF/B-V based library was produced. Use of the SAM-CE program in thermal reactor problems was validated using detailed comparisonsmore » of results with other Monte Carlo codes such as RECAP, RCP01 and VIM as well as with experimental data.« less

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