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Title: Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS

This paper is Included in the session on multiscale multiphysics applications in thermal hydraulics.
Authors:
 [1] ;  [1] ;  [1] ;  [2] ;  [2] ;  [2] ;  [2] ;  [2] ;  [3] ;  [4]
  1. Univ. of Michigan, Ann Arbor, MI (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Core Physics, Inc. (United States)
  4. Westinghouse Electric Company, Cranberry Township (United States)
Publication Date:
OSTI Identifier:
1214019
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: NURETH-16. International Topical Meeting on Nuclear Reactor Hydraulics, Chicago, IL (United States), 30 Aug - 4 Sep 2015
Research Org:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 97 MATHEMATICS AND COMPUTING; THREE-DIMENSIONAL CALCULATIONS; NEUTRON TRANSPORT; THERMAL HYDRAULICS; VALIDATION; M CODES