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Title: Contribution to the validation of MCNP neutronics design of the advanced neutron source reactor

Abstract

In the research and development plan of the advanced neutron source (ANS) reactor, one of the steps planned for neutronics design methods validation is to compare computational model results and experimental results for a critical facility exhibiting similarities with the ANS reactor. One such facility is the FOEHN experiment. In this paper, an MCNP model of the FOEHN experiment is developed, and its results are compared with experimental data from the literature. The MCNP models reproduces measured quantities of interest with a high level of agreement.

Authors:
; ; ;  [1]
  1. (Idaho National Engineering Lab., Idaho Falls (United States))
Publication Date:
OSTI Identifier:
5802904
Alternate Identifier(s):
OSTI ID: 5802904
Report Number(s):
CONF-930601--
Journal ID: ISSN 0003-018X; CODEN: TANSAO
Resource Type:
Conference
Resource Relation:
Journal Name: Transactions of the American Nuclear Society; (United States); Journal Volume: 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; REACTOR PHYSICS; MATHEMATICAL MODELS; REACTORS; COMPUTERIZED SIMULATION; DESIGN; MONTE CARLO METHOD; NEUTRON SOURCES; REACTOR CORES; VALIDATION; CALCULATION METHODS; PARTICLE SOURCES; PHYSICS; RADIATION SOURCES; REACTOR COMPONENTS; SIMULATION; TESTING 220600* -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors; 220100 -- Nuclear Reactor Technology-- Theory & Calculation

Citation Formats

Rubio, G.A., Ougouag, A.M., Wemple, C.A., and Ryskamp, J.M. Contribution to the validation of MCNP neutronics design of the advanced neutron source reactor. United States: N. p., 1993. Web.
Rubio, G.A., Ougouag, A.M., Wemple, C.A., & Ryskamp, J.M. Contribution to the validation of MCNP neutronics design of the advanced neutron source reactor. United States.
Rubio, G.A., Ougouag, A.M., Wemple, C.A., and Ryskamp, J.M. Fri . "Contribution to the validation of MCNP neutronics design of the advanced neutron source reactor". United States. doi:.
@article{osti_5802904,
title = {Contribution to the validation of MCNP neutronics design of the advanced neutron source reactor},
author = {Rubio, G.A. and Ougouag, A.M. and Wemple, C.A. and Ryskamp, J.M.},
abstractNote = {In the research and development plan of the advanced neutron source (ANS) reactor, one of the steps planned for neutronics design methods validation is to compare computational model results and experimental results for a critical facility exhibiting similarities with the ANS reactor. One such facility is the FOEHN experiment. In this paper, an MCNP model of the FOEHN experiment is developed, and its results are compared with experimental data from the literature. The MCNP models reproduces measured quantities of interest with a high level of agreement.},
doi = {},
journal = {Transactions of the American Nuclear Society; (United States)},
number = ,
volume = 68,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1993},
month = {Fri Jan 01 00:00:00 EST 1993}
}

Conference:
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  • A summary of the methods and models used to perform neutronics analyses on the Advanced Neutron Source reactor three-element core design is presented. The applications of the neutral particle Monte Carlo code MCNP are detailed, as well as the expansion of the static role of MCNP to analysis of fuel cycle depletion calculations. Results to date of these applications are presented also. A summary of the calculations not yet performed is also given to provide a {open_quotes}to-do{close_quotes} list if the project is resurrected.
  • The Idaho National Laboratory (INL) is in the process of modernizing the various reactor physics modeling and simulation tools used to support operation and safety assurance of the Advanced Test Reactor (ATR). Key accomplishments so far have encompassed both computational as well as experimental work. A new suite of stochastic and deterministic transport theory based reactor physics codes and their supporting nuclear data libraries (HELIOS, KENO6/SCALE, NEWT/SCALE, ATTILA, and an extended implementation of MCNP5) has been installed at the INL. Corresponding models of the ATR and ATRC are now operational with all five codes, demonstrating the basic feasibility of themore » new code packages for their intended purpose. Of particular importance, a set of as-run core depletion HELIOS calculations for all ATR cycles since August 2009 was successfully completed during 2011. This demonstration supported a decision late in the year to proceed with the phased incorporation of the HELIOS methodology into the ATR fuel cycle management process beginning in 2012. On the experimental side of the project, new hardware was fabricated, measurement protocols were finalized, and the first four of six planned physics code validation experiments based on neutron activation spectrometry were conducted at the ATRC facility. Data analysis for the first three experiments, focused on characterization of the neutron spectrum in one of the ATR flux traps, has been completed. The six experiments will ultimately form the basis for a flexible, easily-repeatable ATR physics code validation protocol that is consistent with applicable ASTM standards.« less
  • The Idaho National Laboratory (INL) is in the process of updating the various reactor physics modeling and simulation tools used to support operation and safety assurance of the Advanced Test Reactor (ATR). Key accomplishments so far have encompassed both computational as well as experimental work. A new suite of stochastic and deterministic transport theory based reactor physics codes and their supporting nuclear data libraries (HELIOS, KENO6/SCALE, NEWT/SCALE, ATTILA, and an extended implementation of MCNP5) has been installed at the INL. Corresponding models of the ATR and ATRC are now operational with all five codes, demonstrating the basic feasibility of themore » new code packages for their intended purposes. On the experimental side of the project, new hardware was fabricated, measurement protocols were finalized, and the first four of six planned physics code validation experiments based on neutron activation spectrometry have been conducted at the ATRC facility. Data analysis for the first three experiments, focused on characterization of the neutron spectrum in one of the ATR flux traps, has been completed. The six experiments will ultimately form the basis for flexible and repeatable ATR physics code validation protocols that are consistent with applicable national standards. (authors)« less
  • Two areas concerned with the design of the Advanced Neutron Source (ANS) cold source have been investigated by simple one-dimensional calculations. The gain factors computed for a possible liquid nitrogen-15 cold source moderator are considerably below those computed for the much colder liquid deuterium moderator, as is reasonable considering the difference in moderator temperature. Nevertheless, nitrogen-15 does represent a viable option should safety related issues prohibit the use of deuterium as a moderating material. The slab geometry calculations have indicated that reflection of neutrons may be the dominant moderating mechanism and should be a consideration in the design of themore » cold source. 9 refs., 2 figs.« less
  • Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL) have been jointly working to develop and evaluate preconceptual reactor core configurations for the advanced neutron source. This paper reviews the reactor physics methods used to compute reactor parameters and demonstrates that the laboratories achieve good agreement on these parameters.