FAST REACTOR CROSS-SECTION PROCESSING CODES - IS THERE A DOLLARS WORTH OF DIFFERENCE BETWEEN THEM?

Author:

Weisbin C.R.,Greene N.M.,Henryson H.,LaBauve R.J.,Durston C.,Cullen D.E.,Kidman R.B.

Publisher

Elsevier

Reference47 articles.

1. “The AMPX Modular Code System for Generating Coupled Neutron-Gamma Multigroup Cross-Section Sets,”;Greene;Trans, Am, Nucl, Soc,1972

2. “MINX – A Multigroup Interpretation of Nuclear X-sections,”;Weisbin;Trans, Am, Nucl, Soc,1973

3. D. R. Harris, R. J. LaBauve, R. E. MacFarlane, and P. D. Soran, Los Alamos Scientific Laboratory, and C. R. Weisbin and J. E. White, Oak Ridge National Laboratory, “MINX, A Modular Code System for Processing Multigroup Cross Sections from Nuclear Data in ENDF/B Format,” LA-UR-1766, presented at the Seminar on Codes for Nuclear Data Processing held at NEA-CPL, CONF-731207–1, Ispra, December 5–7, 1973.

4. N. C. Paik, C. Durston, W. Davis, and M. B. Yarbrough, “Physics Evaluations and Applications - Quarterly Progress Report for Period Ending January 31, 1974,” WARD-XS-3045–5 (March 1974).

5. H. Henryson, II, B. J. Toppel, and C. G. Stenberg, “ETOE-2/MC2-2/SDX Multigroup Neutron Cross-Section Processing,” presented at the Seminar on Codes for Nuclear Data Processing held at NEA-CPL, CONF-731207–1, Ispra, December 5–7, 1973; see also B. J. Toppel and H. Henryson, II, “Methodology and Application of the MC2-2/SDX Cross Section Capability,” Trans, Am, Nucl, Soc., 16, 126(1973).

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1. The applicability study and validation of TULIP code for full energy range spectrum;Nuclear Engineering and Technology;2023-12

2. Calculational Methodology and Associated Uncertainties;Advances in Nuclear Science and Technology;1982

3. DEVELOPMENTS IN PERTURBATION THEORY;Advances in Nuclear Science and Technology;1976

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