Libros sobre el tema "NUCLEUS SOFTWARE"

Agency, International Atomic Energy, ed. 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. y American Association of Physicists in Medicine., eds. 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.) y U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. 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., ed. 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., ed. 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., ed. 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 y U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. 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., ed. 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., ed. 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, ed. 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., ed. 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, ed. 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 y National Institute of Standards and Technology (U.S.), eds. 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 y U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., eds. 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, ed. 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, ed. 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, ed. 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. y Science and Engineering Associates, eds. 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 y Bhabha Atomic Research Centre, eds. 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. y Oak Ridge National Laboratory, eds. 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 y U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., eds. 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 y Winfrith Technology Centre, eds. WIMS-D library update. Vienna, Austria: International Atomic Energy Agency, 2007.

Agency, International Atomic Energy, ed. 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. y SoHaR Incorporated, eds. 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 y U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., eds. 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, ed. 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. y SoHaR Incorporated, eds. 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. y Bhabha Atomic Research Centre, eds. 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.