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Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V, and ENDF/B-VI iron evaluations / prepared by M.L. Williams ... [et al.] ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

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Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V, and ENDF/B-VI iron evaluations / prepared by M.L. Williams ... [et al.] ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Call No. (NDL)
YCA-Y 3.N 88:25/5648
Bibliographic ID of National Diet Library
000006592447
Material type
図書
Author
Williams, M. Lほか
Publisher
-
Publication date
1991
Material Format
Microform
Capacity, size, etc.
microfiche ; 11 × 15 cm
NDC
-
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Notes on use

Note (General)：

"Oak Ridge National Laboratory."Distributed to depository libraries in microfiche"Date published: April 1991."...

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Microform

Material Type
図書
Title
Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V, and ENDF/B-VI iron evaluations / prepared by M.L. Williams ... [et al.] ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Author Heading
Williams, M. L
Oak Ridge National Laboratory
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering
Publication Date (W3CDTF)
1991
Extent
microfiche
Size
11 × 15 cm
Place of Publication (Country Code)
US
Text Language Code
eng
Note (Material Type)
[microform]
Subject Heading
Neutron cross sections -- Measurement
Steel -- Effect of radiation on
Nuclear pressure vessels -- Effect of radiation on