Neutron fission chain behavior for modern 235U multiplicity data-Reference-Cited by-同舟云学术

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Neutron fission chain behavior for modern 235U multiplicity data

Published:2024-03 Issue: Volume:168 Page:104946
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Durkee Joe W.^ORCID

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference82 articles.

1. Handbook of Mathematical Functions;Abramowitz,1972

2. An Introduction to the Theory of Groups;Alexandroff,2012

3. Basic Abstract Algebra;Ash,2007

4. “DSN: A CDC-7600 FORTRAN Program for the Calculation of One-Dimensional, Multigroup Neutron Transport, Worth, and Persistent Fission Chain Probability,” Los Alamos National Laboratory Report LA-4897;Asprey,1976

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