00656nam0-2200253 --450 991059419360332120221006181726.0978069115404620221006d2020----kmuy0itay5050 baengengUS 001yyDanteJohn TookPrincetonPrinceton University Press2020XXIII, 609 p.23 cm851.123Took,J. F.802004ITUNINAREICATUNIMARCBK9910594193603321851.1 DANTE/S 5132022/2039FLFBCFLFBCDante2493646UNINA01797nam 2200445I 450 991070778000332120161028153812.0(CKB)5470000002466746(OCoLC)961359366(EXLCZ)99547000000246674620161028d1992 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAnalysis of semiscale test S-LH-1 using RELAP5/MOD2 /prepared by P.C. Hall, D.R. BullWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,1992.1 online resource (v, 32 pages) illustrationsInternational agreement report ;NUREG/IA-0064"National Power Nuclear, Barnett Way.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP).""April 1992.""GD/PE-N/725.""PWR/HTWG/P(88)629(Rev)."Includes bibliographical references.Analysis of semiscale test S LH 1 using RELAP5/MOD2Pressurized water reactorsTestingEmergency core cooling systemsTestingPressurized water reactorsTesting.Emergency core cooling systemsTesting.Hall P. C(Peter C.),1404634Bull D. R(David R.),U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910707780003321Analysis of semiscale test S-LH-1 using RELAP53539476UNINA