Evaluation and Propagation of the239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique-Reference-Cited by-同舟云学术

Evaluation and Propagation of the239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique

Published:2006-05 Issue:1 Volume:153 Page:1-7
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Kawano T.¹,Hanson K. M.¹,Frankle S.¹,Talou P.¹,Chadwick M. B.¹,Little R. C.¹

Affiliation:

1. Los Alamos National Laboratory Los Alamos, New Mexico 87545

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE06-A2589

Reference20 articles.

1. Development of a Unified Cross-section Set ADJ2000 based on Adjustment Technique for Fast Reactor Analysis

2. Critical Experiment Programs at the Los Alamos National Laboratory in Support of the U.S. Department of Energy/National Nuclear Security Administration’s Nuclear Criticality Safety Program

3. “International Handbook of Evaluated Criticality Safety Benchmark Experiment,” NEA/NSC/DOC(95)03, Organisation for Economic Cooperation and Development/Nuclear Energy Agency (2002).

4. D. L. SMITH, “Probability, Statistics, and Data Uncertainties in Nuclear Science and Technology,” OECD/NEA, American Nuclear Society, La Grange Park, Illinois (1991).

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