Randomly dispersed particle fuel model in the PSG Monte Carlo neutron transport code

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

8 Citations (Scopus)

Abstract

High-temperature gas-cooled reactor fuels are composed of thousands of microscopic fuel particles, randomly dispersed in a graphite matrix. The modelling of such geometry is complicated, especially using continuous-energy Monte Carlo codes, which are unable to apply any deterministic corrections in the calculation. This paper presents the geometry routine developed for modelling randomly dispersed particle fuels using the PSG Monte Carlo reactor physics code. The model is based on the delta-tracking method, and it takes into account the spatial self-shielding effects and the random dispersion of the fuel particles. The calculation routine is validated by comparing the results to reference MCNP4C calculations using uranium and plutonium based fuels.
Original languageEnglish
Title of host publicationMathematics and Computations and Supercomputing in Nuclear Applications (M&C+SNA 2007)
Subtitle of host publicationMonterey, CA, April 15-19, 2007
PublisherAmerican Nuclear Society ANS
Number of pages12
ISBN (Electronic)978-0-89448-059-1, 0-89448-059-6
Publication statusPublished - 2007
MoE publication typeA4 Article in a conference publication
EventJoint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M&C + SNA 2007 - Monterey, United States
Duration: 15 Apr 200719 Apr 2007

Conference

ConferenceJoint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M&C + SNA 2007
CountryUnited States
CityMonterey
Period15/04/0719/04/07

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    Leppänen, J. (2007). Randomly dispersed particle fuel model in the PSG Monte Carlo neutron transport code. In Mathematics and Computations and Supercomputing in Nuclear Applications (M&C+SNA 2007): Monterey, CA, April 15-19, 2007 American Nuclear Society ANS.