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035 a| (Sirsi) o870971006;

043 a| n-us---;

049 a| ERE#;

074 a| 1051-H-41 (online);

086 0 a| Y 3.N 88:53/0435;

100 1 a| Kynčl, M,e| author.?| UNAUTHORIZED;

245 10 a| Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility /c| prepared by M. Kynčl, R. Pernica.;

264 1 a| Washington, DC :b| United States Nuclear Regulatory Commission,c| 2013.;

300 a| 1 online resource (xvi, 183 pages) :b| color illustrations.;

336 a| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

490 1 a| International agreement report ;v| NUREG/IA-0435;

500 a| "December 2013.";

500 a| Title from title screen (viewed on Feb. 24, 2014).;

500 a| "Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP).";

504 a| Includes bibliographical references (pages 83-84).;

650 0 a| Pressurized water reactorsx| Loss of coolantx| Computer simulation.=| ^A684932;

650 0 a| Nuclear facilitiesx| Computer programs.=| ^A269004;

700 1 a| Pernica, R.,e| author.?| UNAUTHORIZED;

710 2 a| U.S. Nuclear Regulatory Commissione| issuing body.=| ^A198030;

776 08 i| Paper version:a| Kynčl, M.t| Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facilityw| (OCoLC)870970931;

830 0 a| International agreement reportv| NUREG/IA-0435.=| ^A463558;

856 40 u| https://purl.fdlp.gov/GPO/gpo46257;

949 a| Click on web addressw| ASISh| JOYNER94;

998 a| 3446789;

998 a| u3446789;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 3446789-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 3/17/2014x| EDOCUMENTz| JERESOURCE;

Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility / prepared by M. Kynčl, R. Pernica.

Author/creator	Kynčl, M author.
Other author	Pernica, R., author.
Other author	U.S. Nuclear Regulatory Commission issuing body.
Format	Electronic
Publication	Washington, DC : United States Nuclear Regulatory Commission, 2013.
Description	1 online resource (xvi, 183 pages) : color illustrations.
Supplemental Content	https://purl.fdlp.gov/GPO/gpo46257
Subjects	Pressurized water reactors--Loss of coolant. --Computer simulation. Nuclear facilities--Computer programs.

Series	International agreement report ; NUREG/IA-0435 International agreement report NUREG/IA-0435. ^A463558
General note	"December 2013."
General note	Title from title screen (viewed on Feb. 24, 2014).
General note	"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
Bibliography note	Includes bibliographical references (pages 83-84).
Issued in other form	Paper version: Kynčl, M. Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility
GPO item number	1051-H-41 (online)
Govt. docs number	Y 3.N 88:53/0435

Assessment of RELAP5/MOD3.3 and TRACE V5.0 computer codes against LOCA test data from PSB-VVER test facility / prepared by M. Kynčl, R. Pernica.

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