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Title: Progress with On-The-Fly Neutron Doppler Broadening in MCNP

The University of Michigan, ANL, and LANL have been collaborating on a US-DOE-NE University Programs project 'Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors.' This talk describes the project and provides results from the initial implementation of On-The-Fly Doppler broadening (OTF) in MCNP and testing. The OTF methodology involves high precision fitting of Doppler broadened cross-sections over a wide temperature range (the target for reactor calculations is 250-3200K). The temperature dependent fits are then used within MCNP during the neutron transport, for OTF broadening based on cell temperatures. It is straightforward to extend this capability to cover any temperature range of interest, allowing the Monte Carlo simulation to account for a continuous distribution of temperature ranges throughout the problem geometry.
Authors:
 [1] ;  [1] ;  [2] ;  [3]
  1. Los Alamos National Laboratory
  2. Argonne National Laboratory
  3. University of Michigan
Publication Date:
OSTI Identifier:
1044100
Report Number(s):
LA-UR-12-22277
TRN: US1203330
DOE Contract Number:
AC52-06NA25396
Resource Type:
Conference
Resource Relation:
Conference: 2012 ANS Summer Meeting ; 2012-06-24 - 2012-06-28 ; Chicago, Illinois, United States
Research Org:
Los Alamos National Laboratory (LANL)
Sponsoring Org:
DOE/LANL
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; 97 MATHEMATICAL METHODS AND COMPUTING; ACCURACY; ANL; CROSS SECTIONS; DISTRIBUTION; DOPPLER BROADENING; GEOMETRY; IMPLEMENTATION; LANL; NEUTRON TRANSPORT; NEUTRONS; SIMULATION; TARGETS; TESTING