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001 ocn874154076;

003 OCoLC;

005 20141212064253.0;

006 m o d f ;

007 cr mn||||a||||;

008 140321s2014 dcua ob f000 0 eng c;

035 a| (Sirsi) o874154076;

042 a| pcc;

049 a| ERE#;

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

086 0 a| Y 3.N 88:25/7172;

100 1 a| Natesan, K.q| (Krishnamurti),d| 1942-e| author.=| ^A786280;

245 10 a| Development of quantitative software reliability models for digital protection systems of nuclear power plants /c| prepared by K. Natesan [and three others].;

264 1 a| Washington, D.C. :b| United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,c| 2014.;

300 a| 1 online resource (469 unnumbered pages) :b| color illustrations;

336 a| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

500 a| Title from title screen (viewed on Mar. 21, 2014).;

500 a| "January 2014.";

500 a| "NUREG/CR-7172.";

500 a| "ANL-10/38.";

504 a| Includes bibliographical references (pages 9-1-9-12).;

650 0 a| Light water reactorsx| Accidentsx| Prevention.=| ^A443802;

650 0 a| Pumping stationsx| Safety measures.=| ^A8722;

650 0 a| Pressurized water reactorsx| Loss of coolantx| Safety measures.=| ^A684932;

650 0 a| Water cooled reactorsx| Loss of coolantx| Safety measures.=| ^A444383;

650 0 a| Nuclear power plantsx| Safety measures.=| ^A176090;

710 2 a| U.S. Nuclear Regulatory Commission.b| Office of Nuclear Regulatory Researche| issuing body.=| ^A420721;

710 2 a| Argonne National Laboratory.=| ^A12819;

776 08 i| Print version:a| Natesan, K. (Krishnamurti), 1942-.t| Development of quantitative software reliability models for digital protection systems of nuclear power plantsw| (OCoLC)874153745;

856 40 u| https://purl.fdlp.gov/GPO/gpo46967;

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

998 a| 3452308;

998 a| u3452308;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 3452308-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 4/3/2014x| EDOCUMENTz| JERESOURCE;

Development of quantitative software reliability models for digital protection systems of nuclear power plants / prepared by K. Natesan [and three others].

Author/creator	Natesan, K., 1942- author.
Other author	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research issuing body.
Other author	Argonne National Laboratory.
Format	Electronic
Publication	Washington, D.C. : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2014.
Description	1 online resource (469 unnumbered pages) : color illustrations
Supplemental Content	https://purl.fdlp.gov/GPO/gpo46967
Subjects	Light water reactors--Accidents. --Prevention. Pumping stations--Safety measures. Pressurized water reactors--Loss of coolant. --Safety measures. Water cooled reactors--Loss of coolant. --Safety measures. Nuclear power plants--Safety measures.

General note	Title from title screen (viewed on Mar. 21, 2014).
General note	"January 2014."
General note	"NUREG/CR-7172."
General note	"ANL-10/38."
Bibliography note	Includes bibliographical references (pages 9-1-9-12).
Issued in other form	Print version: Natesan, K. (Krishnamurti), 1942-. Development of quantitative software reliability models for digital protection systems of nuclear power plants
GPO item number	1051-H-11 (online)
Govt. docs number	Y 3.N 88:25/7172

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Development of quantitative software reliability models for digital protection systems of nuclear power plants / prepared by K. Natesan [and three others].

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