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Assessment of BISON capabilities for component-level prediction of tritium transport in fusion and fission applications

  • Published:2022-02 Issue: Volume:175 Page:112996
  • ISSN:0920-3796
  • Container-title:Fusion Engineering and Design
  • language:en
  • Short-container-title:Fusion Engineering and Design

Author:

O'Neal Miles,Seo Seok Bin,Maldonado G. Ivan,Brown Nicholas R.

Funder

Oak Ridge National Laboratory

U.S. Department of Energy

Office of Nuclear Energy

Fusion Energy Sciences

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference52 articles.

1. DOE. STD 6002-96, Safety of magnetic fusion facilities, 1996.

2. Hydrogen in zirconium alloys: a review;Motta;J. Nucl. Mater.,2019

3. Tritium Transport, Corrosion, and Fuel Performance Modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR);Stempien,2015

4. Tritium in nitride fuel of fast reactors;Ustinov;At. Energy,2019

5. Evaluation of stainless steel cladding for use in current design LWRs;Strasser;Final Rep.,1982

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