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035   $a(CKB)5470000002465391
035   $a(OCoLC)645870979$z(OCoLC)300976061
035   $a(EXLCZ)995470000002465391
100   $a20100703j198609    ua             0
101 0 $aeng
135   $aurbn||||||ada
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAssessment of RELAP5/MOD 2 against critical flow data from Marviken tests JIT 11 and CFT 21 /$fprepared by O?. Rosdahl, D. Caraher
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dSeptember 1986.
215   $a1 online resource (various pagings) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0007
300   $aTitle from title screen (Aug. 26, 2016).
300   $a"Swedish Nuclear Power Inspectorate."
300   $a"September 1986."
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"Sponsoring organization: Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.
300   $a"STUDSVIK/NP-86/99"--Bibliographic data sheet.
320   $aIncludes bibliographical references.
517 1 $aStudsvik energiteknik AB
606   $aNuclear pressure vessels
606   $aLight water reactors$xData processing
606   $aNuclear power plants$xThermodynamics
606   $aNuclear reactor kinetics
615  0$aNuclear pressure vessels.
615  0$aLight water reactors$xData processing.
615  0$aNuclear power plants$xThermodynamics.
615  0$aNuclear reactor kinetics.
700   $aRosdahl$b O?$g(O?sten),$01407015
702   $aCaraher$b D$g(David),
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Reactor System Safety,
801  0$bOCLCE
801  1$bOCLCE
801  2$bOCLCQ
801  2$bOCLCO
801  2$bOCLCQ
801  2$bOCLCF
801  2$bOCLCQ
801  2$bGPO
906   $aBOOK
912   $a9910707414103321
996   $aAssessment of RELAP5$93487299
997   $aUNINA