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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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LDR 02185nam a2200445 i 4500
001(Sirsi) o31275082
003OCLC
00519941013090600.0
007he-bmb024bbca
008941013s1992 dcua bbt f000 0 eng d
037 . ‡a052-026-00027-0 ‡bGPO ‡fpaper copy
040 . ‡aGPO ‡erda ‡cGPO ‡dDLC ‡dMvI
074 . ‡a1051-H-41 (MF)
088 . ‡aAEEW-R 2476
0860 . ‡aY 3.N 88:53/0052
1001 . ‡aRogers, J. M. ‡0(EG-IN)1077838
24513. ‡aAn analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2 / ‡cprepared by J.M. Rogers.
264 1. ‡aWashington, DC : ‡bU.S. Nuclear Regulatory Commission ; ‡aSpringfield, Va. : ‡bNational Technical Information Service, [distributor], ‡c[1992]
300 . ‡aviii, 39 pages : ‡billustrations ; ‡c28 cm.
336 . ‡atext ‡btxt ‡2rdacontent
337 . ‡amicroform ‡bh ‡2rdamedia
338 . ‡amicrofiche ‡bhe ‡2rdacarrier
4901 . ‡aInternational agreement report ; ‡vNUREG/IA-0052
513 . ‡aTechnical report.
500 . ‡a"United Kingdom Atomic Energy Authority."
500 . ‡a"Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission."
500 . ‡a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."
500 . ‡aDistributed to depository libraries in microfiche.
500 . ‡aShipping list no.: 92-1555-M.
500 . ‡aNo longer available for sale by the Supt. of Docs.
500 . ‡a"March 1992."
504 . ‡aIncludes bibliographical references (page 12).
500 . ‡a"AEEW-R2476."
536 . ‡cA4682.
533 . ‡aMicrofiche. ‡b[Washington, D.C.?] : ‡cSupt. of Docs., U.S. G.P.O., ‡d[1992] ‡e1 microfiche : negative.
650 0. ‡aPressurized water reactors ‡xEmergency core cooling systems ‡xTesting.
7102 . ‡aUnited Kingdom Atomic Energy Authority. ‡0(EG-IN)1165120
7102 . ‡aU.S. Nuclear Regulatory Commission. ‡bOffice of Nuclear Regulatory Research. ‡0(EG-IN)1310199
830 0. ‡aInternational agreement report ‡0(EG-IN)1360980
901 . ‡a(Sirsi) o31275082 ‡bOCLC ‡c17274946 ‡tbiblio

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