ESTIMATED DATA COVARIANCE FILES OF EVALUATED CROSS SECTIONS — EXAMPLES FOR 235U AND 238 U-Reference-Cited by-同舟云学术

ESTIMATED DATA COVARIANCE FILES OF EVALUATED CROSS SECTIONS — EXAMPLES FOR 235U AND 238 U

Published:1975 Issue: Volume: Page:578-591
ISSN:
Container-title:Advanced Reactors: Physics, Design and Economics
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Author:

Perey F.G.,de Saussure G.,Perez R.B.

Publisher

Elsevier

Reference24 articles.

1. P. Greebler, B. A. Hutchins and C. L. Cowan, Implications of Nuclear Data Uncertainties to Reactor Design, Nuclear Data for Reactors, Proc. Conf. Helsinki (1970). Vienna, IAEA, 1970, Vol. I, 17.

2. J. Y. Barré and J. P. Chaudat, Roles Respectifs des Evaluations et des Expériences Intégrals pour la Physique des Réacteurs Rapides, Applications of Nuclear Data in Science and Technology, Symp. Paris (1973). paper IAEA/SM-170/91.

3. L. N. Usachev, V. N. Manokhin and Y. G. Bokkov, Nuclear Data Accuracies and Their Implications on the Design of Fast Reactors, Applications of Nuclear Data in Science and Technology, Symp. Paris (1973). paper IAEA/SM-170/91.

4. H. H. Hummel and W. M. Stacey, Jr., FRA-TM-54, ANL (1973).

5. Minutes of the Spring and Fall 1973 Meeting of the Cross-Section Evaluation Working Group and F. G. Perey, “Formats and Procedures for ENDF/B Data Covariance Files,” to be published.

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1. New Perspective in Covariance Evaluation for Nuclear Data;Nuclear Data for Science and Technology;1992

2. Uncertainty in the Nuclear Data Used for Reactor Calculations;Advances in Nuclear Science and Technology;1982

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