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003 OCoLC;

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035 a| (Sirsi) o921844183;

042 a| pcc;

043 a| n-us---;

049 a| ERE#;

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

086 0 a| Y 3.N 88:25/7205;

088 a| NUREG/CR-7205;

088 a| ORNL/TM-2012/544;

100 1 a| Mueller, D. E.,e| author.=| ^A1154557;

245 10 a| Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks /c| prepared by D.E. Mueller [and three others].;

264 1 a| Washington, DC :b| U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards,c| September 2015.;

300 a| 1 online resource (73 unnumbered pages) :b| color illustrations;

336 a| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

500 a| "Manuscript completed: May 2014; Date published: September 2015.";

500 a| Title from title screen (viewed on Sept. 18, 2015).;

500 a| "NUREG/CR-7205.";

500 a| "ORNL/TM-2012/544.";

504 a| Includes bibliographical references (page 21).;

650 0 a| Fission productsx| Handling.=| ^A272979;

650 0 a| Monte Carlo method.=| ^A37649;

650 0 a| Actinide elements.=| ^A29913;

650 0 a| Fuel burnup (Nuclear engineering)=| ^A690721;

650 0 a| Spent reactor fuelsx| Storage.=| ^A440402;

650 0 a| Spent reactor fuelsx| Transportation.=| ^A115453;

650 0 a| Pressurized water reactors.=| ^A102373;

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

710 2 a| Oak Ridge National Laboratory,e| issuing body.=| ^A13009;

776 08 i| Print version:a| Mueller, D. E.t| Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casksw| (OCoLC)920875940;

856 40 u| https://purl.fdlp.gov/GPO/gpo61036;

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

998 a| 3831648;

998 a| u3831648;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 3831648-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 10/12/2015x| EDOCUMENTz| JERESOURCE;

Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks / prepared by D.E. Mueller [and three others].

Author/creator	Mueller, D. E. author.
Other author	U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards, issuing body.
Other author	Oak Ridge National Laboratory, issuing body.
Format	Electronic
Publication	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, September 2015.
Description	1 online resource (73 unnumbered pages) : color illustrations
Supplemental Content	https://purl.fdlp.gov/GPO/gpo61036
Subjects	Fission products--Handling. Monte Carlo method. Actinide elements. Fuel burnup (Nuclear engineering) Spent reactor fuels--Storage. Spent reactor fuels--Transportation. Pressurized water reactors.

General note	"Manuscript completed: May 2014; Date published: September 2015."
General note	Title from title screen (viewed on Sept. 18, 2015).
General note	"NUREG/CR-7205."
General note	"ORNL/TM-2012/544."
Bibliography note	Includes bibliographical references (page 21).
Issued in other form	Print version: Mueller, D. E. Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks
Technical rpt number	NUREG/CR-7205
Technical rpt number	ORNL/TM-2012/544
GPO item number	1051-H-11 (online)
Govt. docs number	Y 3.N 88:25/7205

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Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks / prepared by D.E. Mueller [and three others].

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