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Title: Implementation of variance reduction methods for efficient Monte Carlo criticality calculations of gaseous core reactors

Abstract

Gas core reactor (GCR) research efforts at the Innovative Nuclear Space Power Institute (INSPI) of the University of Florida currently focus on ultrahigh-temperature vapor core reactors (UTVRs) using magnetohydrodynamic energy conversion with direct nuclear-driven, nonequilibrium ionization of the working fluid as a power source for burst-mode multimegawatt space power. The vapor core reactor concept currently being investigated at INSPI employs uranium tetrafluoride (UF[sub 4]) as the fissile fuel and metal fluoride (KF, NaF, or LiF[sup 7]) as the working fluid. This summary describes the efforts in identification and implementation of vapor core reactor-specific variance reduction techniques in the generalized-geometry, continuous-energy Monte Carlo Transport code, MCNP in order to increase the efficiency of GCR criticality (KCODE) calculations on the CRAY Y-MP8/864 at the San Diego Supercomputer Center.

Authors:
;  [1]
  1. Univ. of Florida, Gainesville (United States)
Publication Date:
OSTI Identifier:
6844727
Report Number(s):
CONF-901101-
Journal ID: ISSN 0003-018X; CODEN: TANSAO
Resource Type:
Conference
Journal Name:
Transactions of the American Nuclear Society; (United States)
Additional Journal Information:
Journal Volume: 62; Conference: American Nuclear Society (ANS) winter meeting, Washington, DC (United States), 11-16 Nov 1990; Journal ID: ISSN 0003-018X
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SPACE POWER REACTORS; REACTOR CORES; REACTOR PHYSICS; CRITICALITY; EFFICIENCY; LITHIUM FLUORIDES; M CODES; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; POTASSIUM FLUORIDES; PULSED REACTORS; RESEARCH PROGRAMS; SODIUM FLUORIDES; URANIUM FLUORIDES; ACTINIDE COMPOUNDS; ALKALI METAL COMPOUNDS; CALCULATION METHODS; COMPUTER CODES; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; LITHIUM COMPOUNDS; LITHIUM HALIDES; MOBILE REACTORS; NEUTRAL-PARTICLE TRANSPORT; PHYSICS; POTASSIUM COMPOUNDS; POWER REACTORS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS; SODIUM COMPOUNDS; URANIUM COMPOUNDS; NESDPS Office of Nuclear Energy Space and Defense Power Systems; 210600* - Power Reactors, Auxiliary, Mobile Package, & Transportable

Citation Formats

Panicker, M M, and Dugan, E T. Implementation of variance reduction methods for efficient Monte Carlo criticality calculations of gaseous core reactors. United States: N. p., 1990. Web.
Panicker, M M, & Dugan, E T. Implementation of variance reduction methods for efficient Monte Carlo criticality calculations of gaseous core reactors. United States.
Panicker, M M, and Dugan, E T. 1990. "Implementation of variance reduction methods for efficient Monte Carlo criticality calculations of gaseous core reactors". United States.
@article{osti_6844727,
title = {Implementation of variance reduction methods for efficient Monte Carlo criticality calculations of gaseous core reactors},
author = {Panicker, M M and Dugan, E T},
abstractNote = {Gas core reactor (GCR) research efforts at the Innovative Nuclear Space Power Institute (INSPI) of the University of Florida currently focus on ultrahigh-temperature vapor core reactors (UTVRs) using magnetohydrodynamic energy conversion with direct nuclear-driven, nonequilibrium ionization of the working fluid as a power source for burst-mode multimegawatt space power. The vapor core reactor concept currently being investigated at INSPI employs uranium tetrafluoride (UF[sub 4]) as the fissile fuel and metal fluoride (KF, NaF, or LiF[sup 7]) as the working fluid. This summary describes the efforts in identification and implementation of vapor core reactor-specific variance reduction techniques in the generalized-geometry, continuous-energy Monte Carlo Transport code, MCNP in order to increase the efficiency of GCR criticality (KCODE) calculations on the CRAY Y-MP8/864 at the San Diego Supercomputer Center.},
doi = {},
url = {https://www.osti.gov/biblio/6844727}, journal = {Transactions of the American Nuclear Society; (United States)},
issn = {0003-018X},
number = ,
volume = 62,
place = {United States},
year = {1990},
month = {1}
}

Conference:
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