Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical

J.J. Wagschal; Atara Ya'ari; Y. Yeivin

Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical

J.J. Wagschal, Atara Ya'ari, Y. Yeivin

Racah Institute of Physics

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The ENDF/B-4 cross sections of the principal isotopes of U and Pu are adjusted by critical-mass data on 15 metallic assemblies. Only very minor cross-section modifications are needed in order for neutronic calculations to reproduce the integral data well within their experimental errors. The nature of the adjustments and the quality of the input integral data are discussed.

Original language	English
Title of host publication	Nuclear Cross Sections and Technology
Subtitle of host publication	Proceedings of a Conference; Washington, D.C. March 3-7, 1975
Editors	R.A. Schrack, C. D. Bowman
Place of Publication	Washington, DC, USA
Publisher	US Department of Commerce
Pages	405 - 8
Volume	I
State	Published - 1975

Publication series

Name	National Bureau of Standards Special Publication
Number	425

Bibliographical note

integral data;ENDF/B-4 library;cross sections;neutronic calculations;U isotopes;Pu isotopes;

Keywords

fission reactor fuel
fission reactor theory and design
neutron-nucleus reactions
nuclei with mass number 220 or higher
physics computing

Cite this

Wagschal, J. J., Ya'ari, A., & Yeivin, Y. (1975). Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical. In R. A. Schrack, & C. D. Bowman (Eds.), Nuclear Cross Sections and Technology: Proceedings of a Conference; Washington, D.C. March 3-7, 1975 (Vol. I, pp. 405 - 8). (National Bureau of Standards Special Publication ; No. 425). US Department of Commerce.

Wagschal, J.J. ; Ya'ari, Atara ; Yeivin, Y. / Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical. Nuclear Cross Sections and Technology: Proceedings of a Conference; Washington, D.C. March 3-7, 1975. editor / R.A. Schrack ; C. D. Bowman. Vol. I Washington, DC, USA : US Department of Commerce, 1975. pp. 405 - 8 (National Bureau of Standards Special Publication ; 425).

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abstract = "The ENDF/B-4 cross sections of the principal isotopes of U and Pu are adjusted by critical-mass data on 15 metallic assemblies. Only very minor cross-section modifications are needed in order for neutronic calculations to reproduce the integral data well within their experimental errors. The nature of the adjustments and the quality of the input integral data are discussed.",

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author = "J.J. Wagschal and Atara Ya'ari and Y. Yeivin",

note = "integral data;ENDF/B-4 library;cross sections;neutronic calculations;U isotopes;Pu isotopes;",

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Wagschal, JJ, Ya'ari, A & Yeivin, Y 1975, Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical. in RA Schrack & CD Bowman (eds), Nuclear Cross Sections and Technology: Proceedings of a Conference; Washington, D.C. March 3-7, 1975. vol. I, National Bureau of Standards Special Publication , no. 425, US Department of Commerce, Washington, DC, USA, pp. 405 - 8.

Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical. / Wagschal, J.J.; Ya'ari, Atara; Yeivin, Y.
Nuclear Cross Sections and Technology: Proceedings of a Conference; Washington, D.C. March 3-7, 1975. ed. / R.A. Schrack; C. D. Bowman. Vol. I Washington, DC, USA: US Department of Commerce, 1975. p. 405 - 8 (National Bureau of Standards Special Publication ; No. 425).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AU - Ya'ari, Atara

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PY - 1975

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AB - The ENDF/B-4 cross sections of the principal isotopes of U and Pu are adjusted by critical-mass data on 15 metallic assemblies. Only very minor cross-section modifications are needed in order for neutronic calculations to reproduce the integral data well within their experimental errors. The nature of the adjustments and the quality of the input integral data are discussed.

KW - fission reactor fuel

KW - fission reactor theory and design

KW - neutron-nucleus reactions

KW - nuclei with mass number 220 or higher

KW - physics computing

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VL - I

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EP - 408

BT - Nuclear Cross Sections and Technology

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A2 - Bowman, C. D.

PB - US Department of Commerce

CY - Washington, DC, USA

ER -

Wagschal JJ, Ya'ari A, Yeivin Y. Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical. In Schrack RA, Bowman CD, editors, Nuclear Cross Sections and Technology: Proceedings of a Conference; Washington, D.C. March 3-7, 1975. Vol. I. Washington, DC, USA: US Department of Commerce. 1975. p. 405 - 8. (National Bureau of Standards Special Publication ; 425).

Differential cross sections and integral data: the ENDF/B-4 library and `clean' critical

Abstract

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