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LEADER 02894nam 2200565Ia 4500

001 ocn607562127;

003 OCoLC;

005 20141212051722.0;

006 m d ;

007 cr m||||||||||;

008 100416s2009 dcua sbt f000 0 eng d;

035 a| (Sirsi) o607562127;

035 a| (OCoLC)607562127;

040 a| GPOc| GPOd| GPOd| UtOrBLW;

043 a| n-us---;

049 a| ERE#;

074 a| 1051-H-11 (online);

086 0 a| Y 3.N 88:25/6990;

088 a| NUREG/CR-6990;

245 00 a| Development and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6 /c| prepared by D. Wiarda [and others].;

260 a| Washington, DC :b| U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards,c| [2009];

300 a| 1 online resource (140 pages) :b| illustrations (chiefly color);

336 a| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

500 a| Title from PDF title screen (viewed on Apr. 16, 2010).;

500 a| "Date published: February 2009.";

500 a| Performing organization: Oak Ridge National Laboratory.;

500 a| "NUREG/CR-6990.";

500 a| "ORNL/TM-2008/047.";

504 a| Includes bibliographical references (p. 89-90).;

536 a| Sponsored by: Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguardsd| J5609;

650 0 a| Criticality (Nuclear engineering)=| ^A332883;

650 0 a| Neutron cross section standardsv| Databases.=| ^A1017314;

650 0 a| Neutron cross section standardsx| Computer programs.=| ^A1017314;

700 1 a| Wiarda, Dorothea.=| ^A1412325;

710 2 a| U.S. Nuclear Regulatory Commission.b| Office of Nuclear Material Safety and Safeguards.=| ^A425631;

710 2 a| U.S. Nuclear Regulatory Commission.b| Division of Spent Fuel Storage and Transportation.=| ^A793124;

710 2 a| Oak Ridge National Laboratory.=| ^A13009;

776 08 i| Print version:t| Development and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6.d| Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, [2009]w| (OCoLC)607564817;

856 40 u| https://purl.fdlp.gov/GPO/LPS121561;

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

998 a| 2277077;

998 a| u2277077;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 2277077-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 5/18/2010x| EDOCUMENTz| JERESOURCE;

Development and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6 / prepared by D. Wiarda [and others].

Format	Electronic
Publication Info	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, [2009]
Description	1 online resource (140 pages) : illustrations (chiefly color)
Supplemental Content	https://purl.fdlp.gov/GPO/LPS121561
Subjects	Criticality (Nuclear engineering) Nuclear power plants--United States. --Shielding (Radiation). --Data processing. Nuclear power plants--United States. --Shielding (Radiation). --Computer programs. Nuclear reactors--United States. --Shielding (Radiation). --Data processing. Nuclear reactors--Shielding (Radiation). --United States. --Computer programs. Neutron cross section standards--Databases. Neutron cross section standards--Computer programs.

Other author/creator	Wiarda, Dorothea.
Other author/creator	U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards.
Other author/creator	U.S. Nuclear Regulatory Commission. Division of Spent Fuel Storage and Transportation.
Other author/creator	Oak Ridge National Laboratory.
General note	Title from PDF title screen (viewed on Apr. 16, 2010).
General note	"Date published: February 2009."
General note	Performing organization: Oak Ridge National Laboratory.
General note	"NUREG/CR-6990."
General note	"ORNL/TM-2008/047."
Bibliography note	Includes bibliographical references (p. 89-90).
Funding information	Sponsored by: Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards J5609
Issued in other form	Print version: Development and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6. Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, [2009]
Technical rpt number	NUREG/CR-6990
GPO item number	1051-H-11 (online)
Govt. docs number	Y 3.N 88:25/6990

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Development and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6 / prepared by D. Wiarda [and others].

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