STP1228

    Pool Critical Assembly Benchmark Solutions Using MCNP and Threedant

    Published: Jan 1994


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    Abstract

    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.

    Keywords:

    PCA Benchmark, neutron transport, MCNP, THREEDANT, SN, Monte Carlo, discrete ordinates


    Author Information:

    Urban, WT
    Technical Staff Member, Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM

    Alcouffe, RE
    Technical Staff Member, Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM

    Parsons, DK
    Technical Staff Member, Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM

    Marr, DR
    Technical Staff Member, Radiation Transport Group - X−**6, Los Alamos National Laboratory, Los Alamos, NM

    Clark, BA
    Deputy Group Leader, Radiation Transport Group - X−6, Los Alamos National Laboratory, Los Alamos, NM


    Paper ID: STP15131S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP15131S


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