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Title: BISON

Abstract

The Idaho National Laboratory (INL) fuel performance code BISON is a finite element code used to simulate nuclear fuel during irradiation. It contains models for different types of fuel and cladding such as fundamental thermo-physical properties, creep, swelling, porosity, and mechanical interaction. The authors contribute to the code through the development of some of these models, such as newly formulated thermal conductivity, phase redistribution, and thermal expansion models. In addition, solver methods are contributed where appropriate to facilitate calculations. The code is controlled by INL through an export-controlled license similar to other DOE nuclear related codes.

Authors:
 [1];  [1]
  1. LANL
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE
Contributing Org.:
Los Alamos National Laboratory (LANL)
OSTI Identifier:
1369048
Report Number(s):
BISON; 005349MLTPL00
C17055
DOE Contract Number:  
AC52-06NA25396
Resource Type:
Software
Software Revision:
00
Software Package Number:
005349
Software CPU:
MLTPL
Source Code Available:
Yes
Related Software:
Python
Country of Publication:
United States

Citation Formats

Matthews, Christopher, and Unal, Cetin. BISON. Computer software. Vers. 00. USDOE. 17 May. 2017. Web.
Matthews, Christopher, & Unal, Cetin. (2017, May 17). BISON (Version 00) [Computer software].
Matthews, Christopher, and Unal, Cetin. BISON. Computer software. Version 00. May 17, 2017.
@misc{osti_1369048,
title = {BISON, Version 00},
author = {Matthews, Christopher and Unal, Cetin},
abstractNote = {The Idaho National Laboratory (INL) fuel performance code BISON is a finite element code used to simulate nuclear fuel during irradiation. It contains models for different types of fuel and cladding such as fundamental thermo-physical properties, creep, swelling, porosity, and mechanical interaction. The authors contribute to the code through the development of some of these models, such as newly formulated thermal conductivity, phase redistribution, and thermal expansion models. In addition, solver methods are contributed where appropriate to facilitate calculations. The code is controlled by INL through an export-controlled license similar to other DOE nuclear related codes.},
doi = {},
year = {Wed May 17 00:00:00 EDT 2017},
month = {Wed May 17 00:00:00 EDT 2017},
note =
}

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