SYMPOSIA PAPER Published: 01 January 1994
STP15131S

Pool Critical Assembly Benchmark Solutions Using MCNP and Threedant

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Analyses of pressure vessel damage resulting from neutron irradiation have primarily relied on two-dimensional transport calculations and a spatial-synthesis methodology to accommodate three-dimensional effects in the results of two two-dimensional calculations. In this paper, we report on calculations made on the Pool Critical Assembly (PCA) Benchmark, Configuration 12/13, using the three-dimensional, continuous energy Monte Carlo transport code, MCNP, and the three-dimensional, multigroup, diffusion accelerated discrete ordinates transport code THREEDANT. Neutron fluxes and activation rates as determined from these two calculations are compared to each other and to experimental results in the literature. We also draw some conclusions on the value of 3D calculations on the interpretation of experimental results.

Author Information

Urban, WT
Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM
Alcouffe, RE
Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM
Parsons, DK
Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM
Marr, DR
Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM
Clark, BA
Radiation Transport Group - X−6, Los Alamos National Laboratory, Los Alamos, NM
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Details
Developed by Committee: E10
Pages: 376–383
DOI: 10.1520/STP15131S
ISBN-EB: 978-0-8031-5281-6
ISBN-13: 978-0-8031-1899-7