Libri sul tema "NUCLEUS SOFTWARE"

Agency, International Atomic Energy, a cura di. Software for nuclear spectrometry. Vienna, Austria: International Atomic Energy Agency, 1998.

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

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

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

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.

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

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

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., a cura di. 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., a cura di. 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., a cura di. 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.

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.

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.

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

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

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

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

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., a cura di. 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.

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.

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

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

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

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

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

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.

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.

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.

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

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.

W, Bolander T., Idaho National Engineering Laboratory e U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., a cura di. 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.

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

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

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

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

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.

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

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

W, Sciacca F., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Regulatory Applications. e Science and Engineering Associates, a cura di. 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.

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

C, Jordan W., U.S. Nuclear Regulatory Commission. Spent Fuel Project Office. e Oak Ridge National Laboratory, a cura di. 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.

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

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.

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

Agency, International Atomic Energy, e Winfrith Technology Centre, a cura di. WIMS-D library update. Vienna, Austria: International Atomic Energy Agency, 2007.

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

Herbert, Hecht, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology. e SoHaR Incorporated, a cura di. 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.

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

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

Myron, Hecht, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology. e SoHaR Incorporated, a cura di. 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.

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

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.