SYMPOSIA PAPER Published: 01 January 2001

Performance of A MCNP™ for Calculation of 3-D Neutron Flux Distribution in a BWR Core Shroud


This paper analyzes the performance of the A3MCNP™ (Automated Adjoint Accelerated MCNP) for determination of neutron fluence in a BWR core shroud. A3MCNP™ automatically prepares variance reduction parameters based on the CADIS (Consistent Adjoint Driven Importance Sampling) methodology that uses a 3-D energy dependent “importance” function. A3MCNP™ prepares necessary input files for performing adjoint transport calculations using the TORT Sn code. Using A3MCNP™, we have calculated DPA (displacement per atom) values (with a lσ uncertainty) at the H4 weld of a BWR core shroud in less than 5 CPU hour. For the same calculation, an analog Monte Carlo simulation requires about one month of CPU time. The trade-off between the accuracy of the adjoint function calculation and overall computation cost is examined. It is demonstrated that even for a very approximate adjoint function distribution, A3MCNP™ yields significant speedup over an analog Monte Carlo calculation.

Author Information

Haghighat, A
The Pennsylvania State University, University Park, PA, USA
Hiruta, H
The Pennsylvania State University, University Park, PA, USA
Petrovic, B
The Pennsylvania State University, University Park, PA, USA
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Developed by Committee: E10
Pages: 549–556
DOI: 10.1520/STP13641S
ISBN-EB: 978-0-8031-5450-6
ISBN-13: 978-0-8031-2884-2