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An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2 / prepared by J.M. Rogers.

Available copies

  • 1 of 1 copy available at Evergreen Indiana.

Current holds

0 current holds with 1 total copy.

Series Information

International agreement report
Show Only Available Copies
Location Call Number / Copy Notes Barcode Shelving Location Status Due Date
Indiana State Library - Indianapolis Y 3.N 88:53/0052 (Text) 672557-1001 General Federal documents Available -

Record details

  • Physical Description: viii, 39 pages : illustrations ; 28 cm.
  • Publisher: Washington, DC : U.S. Nuclear Regulatory Commission ; [1992]

Content descriptions

General Note:
"United Kingdom Atomic Energy Authority."
"Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission."
"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."
Distributed to depository libraries in microfiche.
Shipping list no.: 92-1555-M.
No longer available for sale by the Supt. of Docs.
"March 1992."
"AEEW-R2476."
Bibliography, etc. Note:
Includes bibliographical references (page 12).
Type of Report and Period Covered Note:
Technical report.
Reproduction Note:
Microfiche. [Washington, D.C.?] : Supt. of Docs., U.S. G.P.O., [1992] 1 microfiche : negative.
Funding Information Note:
A4682.
Subject: Pressurized water reactors > Emergency core cooling systems > Testing.

Series Information

International agreement report

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