Książki na temat „NUCLEUS SOFTWARE”

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1

Agency, International Atomic Energy, red. Software for nuclear spectrometry. Vienna, Austria: International Atomic Energy Agency, 1998.

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2

Rucker, Rudy v. B. Software. London: Roc, 1985.

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3

Rucker, Rudy v. B. Software. Harmondsworth: Penguin, 1985.

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4

A, King Michael, Zimmerman Robert E, Links Jonathan M, Society of Nuclear Medicine (1953- ). Computer Council., Society of Nuclear Medicine (1953- ). Instrumentation Council. i American Association of Physicists in Medicine., red. Imaging hardware and software for nuclear medicine. New York, N.Y: American Institute of Physics, 1988.

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5

Lawrence, J. D. Software safety hazard analysis. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1996.

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6

Hecht, M. Digital systems software requirements guidelines. Washington, DC: U.S. Nuclear Regulatory Commission, 2001.

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7

1961-, Li M., University of Maryland (College Park, Md.) i U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., red. Software engineering measures for predicting software reliability in safety critical digital systems. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.

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8

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., red. Draft regulatory guide DG-1056: Software test documentation for digital computer software used in safety systems of nuclear power plants. [Washington, D.C.]: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1996.

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9

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., red. Draft regulatory guide DG-1058: Software requirements specifications for digital computer software used in safety systems of Nuclear power plants. [Washington, D.C.]: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1996.

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10

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., red. Draft regulatory guide DG-1057: Software unit testing for digital computer software used in safety systems of nuclear power plants. [Washington, D.C.]: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1996.

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11

Lawrence, J. D. Software reliability and safety in nuclear reactor protection systems. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.

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12

Lawrence, Jim. Software reliability and safety in nuclear reactor protection systems. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.

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13

H, Hecht, SoHaR Incorporated i U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., red. Digital systems software requirements guidelines. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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14

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., red. Software quality assurance procedures for NRC thermal hydraulic codes. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.

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15

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., red. Software quality assurance procedures for NRC thermal hydraulic codes. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.

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16

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, red. Software quality assurance procedures for NRC thermal hydraulic codes. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.

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17

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., red. Draft regulatory guide DG-1059: Developing software life cycles processes for digital computer software used in safety systems of nuclear power plants. [Washington, D.C.]: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1996.

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18

Lawrence, J. D. Design factors for safety-critical software. Washington, D.C: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1994.

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19

Green, James A. The effects of thermonuclear weapons. Wyd. 2. Clearwater, Fla. (1280 E. Druid Rd. #11, Clearwater 34616): Greenwood Press, 1991.

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20

Green, James A. The effects of thermonuclear weapons. Wyd. 4. [Wichita, Kan.]: Greenwood Research, 1996.

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21

Software engineering quality practices. Boca Raton, FL: Auerbach Publications, 2005.

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22

U.S. Nuclear Regulatory Commission, red. SOFTWARE ENGINEERING MEASURES FOR PREDICTING SOFTWARE RELIABILITY IN SAFETY CRITICAL DIGITAL SYSTEMS... NUREG/CR-0019... U.S. NUCLEAR REGULA. [S.l: s.n., 2001.

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23

Ross, Paul W. Using Enable: An introduction to integrated software. Boston: Boyd & Fraser, 1988.

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24

Bryant, J. L. Handbook of software quality assurance techniques applicable to the nuclear industry. Washington, DC: Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.

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25

Wallace, Dolores R. High integrity software standards and guidelines. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

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26

Wallace, Dolores R. High integrity software standards and guidelines. Gaithersburg, MD: U.S. Dept. of Commerce, Technology Administration, National Institute of Standards and Technology, 1992.

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27

M, Ippolito Laura, Kuhn D. Richard i National Institute of Standards and Technology (U.S.), red. High integrity software standards and guidelines. Gaithersburg, MD: U.S. Dept. of Commerce, Technology Administration, National Institute of Standards and Technology, 1992.

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28

Wallace, Dolores R. High integrity software standards and guidelines. Gaithersburg, MD: U.S. Dept. of Commerce, Technology Administration, National Institute of Standards and Technology, 1992.

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29

W, Bolander T., Idaho National Engineering Laboratory i U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., red. Verification and validation of the SAPHIRE version 4.0 PRA software package. Washington, D.C: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

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30

Quality assurance and safety software quality assurance, Annular Core Research Reactor. Washington, DC: Defense Nuclear Facilities Safety Board, 2012.

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31

Agency, International Atomic Energy, red. Verification and validation of software related to nuclear power plant instrumentation and control. Vienna: International Atomic Energy Agency, 1999.

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32

D'Angelo, Elizabeth. Software requirements for a nuclear plant operator advisor: The SIPO case study. Toronto: University of Toronto, Dept. of Computer Science, 1997.

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33

Agency, International Atomic Energy, red. Quality assurance for software important to safety. Vienna: International Atomic Energy Agency, 2000.

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34

Miller, L. A. Survey and assessment of conventional software verification and validation methods. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

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35

Argante, Erco. CoCa: A model for parallelization of high energy physics software. Eindhoven: Eindhoven University of Technology, 1998.

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36

Agency, International Atomic Energy, red. Software for computer based systems important to safety in nuclear power plants: Safety guide. Vienna: International Atomic Energy Agency, 2000.

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37

W, Sciacca F., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Regulatory Applications. i Science and Engineering Associates, red. FORECAST: Regulatory effects cost analysis software manual : version 3.0. Washington, DC: Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.

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38

Rajesh, Mishra, i Bhabha Atomic Research Centre, red. Development of a software for the ASME code qualification of class-I nuclear piping systems. Mumbai, India: Bhabha Atomic Research Centre, 1999.

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39

C, Jordan W., U.S. Nuclear Regulatory Commission. Spent Fuel Project Office. i Oak Ridge National Laboratory, red. Guide to verification and validation of the SCALE-4 criticality safety software. Washington, DC: Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1996.

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40

S, Seth, Mitre Corporation i U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., red. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Washington, DC: U.S. Nuclear Regulatory Commission, 1995.

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41

Chu, Tsong-Lun. Development of quantitative software reliability models for digital protection systems of nuclear power plants. Washington, D.C: United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2013.

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42

White, Howard G. Users manual for Nevada Test Site Database (NTS-DB) software. Alexandria, VA: Defense Special Weapons Agency, 1997.

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43

Agency, International Atomic Energy, i Winfrith Technology Centre, red. WIMS-D library update. Vienna, Austria: International Atomic Energy Agency, 2007.

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44

Agency, International Atomic Energy, red. Manual on quality assurance for computer software related to the safety of nuclear power plants. Vienna: International Atomic Energy Agency, 1988.

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45

Herbert, Hecht, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology. i SoHaR Incorporated, red. Review guidelines on software languages for use in nuclear power plant safety systems: Final report. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996.

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46

Myron, Hecht, SoHar Incorporated i U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., red. Review guidelines on software languages for use in nuclear power plant safety systems: Final report. Washington, DC: The Commission, 1996.

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47

U.S. Nuclear Regulatory Commission, red. SOFTWARE QUALITY ASSURANCE PROCEDURES FOR NRC THERMAL HYDRAULIC CODES... NUREG-1737... U.S. NUCLEAR REGULATORY COMMISSION. [S.l: s.n., 2001.

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48

Myron, Hecht, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology. i SoHaR Incorporated, red. Review guidelines for software languages for use in nuclear power plant safety systems: Final report. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.

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49

K, Thiyagarajan T., i Bhabha Atomic Research Centre, red. User manual for XnWlup2.0, a software to visualise nuclear data for thermal reactors in WIMS-D libraries. Mumbai: Bhabha Atomic Research Centre, 2002.

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50

Preckshot, G. G. A proposed acceptance process for commercial off-the-shelf (COTS) software in reactor applications. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1996.

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