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Title: MCNP Progress for NCSP

 [1];  [1];  [1]
  1. Los Alamos National Laboratory
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
Report Number(s):
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: DOE-NNSA Nuclear Criticality Safety Program - Technical Program Review ; 2017-03-14 - 2017-03-15 ; Washington, District Of Columbia, United States
Country of Publication:
United States
MCNP, Monte Carlo, neutron transport, criticality

Citation Formats

Brown, Forrest B., Rising, Michael Evan, and Alwin, Jennifer Louise. MCNP Progress for NCSP. United States: N. p., 2017. Web.
Brown, Forrest B., Rising, Michael Evan, & Alwin, Jennifer Louise. MCNP Progress for NCSP. United States.
Brown, Forrest B., Rising, Michael Evan, and Alwin, Jennifer Louise. Fri . "MCNP Progress for NCSP". United States. doi:.
title = {MCNP Progress for NCSP},
author = {Brown, Forrest B. and Rising, Michael Evan and Alwin, Jennifer Louise},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Mar 03 00:00:00 EST 2017},
month = {Fri Mar 03 00:00:00 EST 2017}

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  • Abstract not provided.
  • 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 capabilitymore » 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.« less
  • Twenty-eight slides give information about the work of the US DOE/NNSA Nuclear Criticality Safety Program on MCNP6 under the following headings: MCNP6.1.1 Release, with ENDF/B-VII.1; Verification/Validation; User Support & Training; Performance Improvements; and Work in Progress. Whisper methodology will be incorporated into the code, and run speed should be increased.
  • The U.S. Department of Energy supports a nuclear criticality safety bibliographic internet database that contains approximately 15,000 records. We are working to ensure that a substantial portion of the corresponding hardcopy documents are preserved, digitized, and made available to criticality safety practitioners via the Nuclear Criticality Safety Program web site.