LEADER 02025nam  2200433I  450 
001 9910707782203321
005 20161028131434.0
035   $a(CKB)5470000002466723
035   $a(OCoLC)961353979
035   $a(EXLCZ)995470000002466723
100   $a20161028j199206    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAnalysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP5/MOD2 /$fprepared by M.J. Dillistone
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJune 1992.
215   $a1 online rsesource (vi, 24 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0071
300   $a"AEEW-M2555."
300   $a"Winfrith Technology Centre, United Kingdom Atomic Energy Authority."
300   $a"June 1992."
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."
300   $a"Type of report: technical"--Bibliographic data sheet.
320   $aIncludes bibliographical references (page 14).
517   $aAnalysis of the UPTF separate effects test 11 
606   $aPressurized water reactors$xAccidents$xData processing
606   $aPressurized water reactors$xTesting$xData processing
615  0$aPressurized water reactors$xAccidents$xData processing.
615  0$aPressurized water reactors$xTesting$xData processing.
700   $aDillistone$b M. J.$01400998
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910707782203321
996   $aAnalysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP5$93468972
997   $aUNINA