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001 9910702530603321
005 20141002110127.0
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035   $a(OCoLC)889447980
035   $a(EXLCZ)995470000002428875
100   $a20140828j201406    ua             0
101 0 $aeng
135   $aurmn||||a||||
181   $2rdacontent
182   $2rdamedia
183   $2rdacarrier
200 10$aResearch reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3 /$fprepared by M. Dabrowski, E. Staron
210  1$aWashington, DC :$cUnited States Nuclear Regulatory Commission,$dJune 2014.
215   $a1 online resource (215 unnumbered pages) $ccolor illustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0443
300   $aTitle from title screen (viewed on Aug. 28, 2014).
300   $a"June 2014."
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
606   $aNuclear reactors$xCooling$zPoland
606   $aNuclear reactors$zPoland$xSafety measures
615  0$aNuclear reactors$xCooling
615  0$aNuclear reactors$xSafety measures.
700   $aDabrowski$b M.$01419676
702   $aStaron$b E.
712 02$aU.S. Nuclear Regulatory Commission,
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910702530603321
996   $aResearch reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3$93534992
997   $aUNINA