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Additional References
Additional References
Essential references specifically related to each chapter of this book have been listed at the end of each chapter. However, these addresses for additional references give the reader a wider choice of documents. The references are grouped as follows: IAEA OECD NRC MISC
International Atomic Energy Agency (www.iaea.org) Organization for Economic Cooperation and Development (www.oecd.org/bookshop) United States Nuclear Regulatory Commission (www.nrc.gov) For references of other sources
IAEA REFERENCES NUCLEAR SAFETY STANDARDS SERIES Safety fundamentals: •
•
•
General safety requirements • Government, legal, and regulatory framework for safety • Leadership and management for safety • Radiation protection and safety of radiation sources • Safety assessment for facilities and activities • Predisposal management of radioactive waste • Decommissioning and termination of activities • Emergency preparedness and response Specific safety requirements • Site evaluation for nuclear installations • Safety of nuclear power plants Design Commissioning and operation • Safety of research reactors • Safety of nuclear fuel cycle facilities • Safety of radioactive waste disposal facilities • Safe transport of radioactive material Collection of safety guides Technical documents TECDOCS INSAG Accidents OECD references
331
332
ADDITIONAL REFERENCES
USNRC references Regulatory Guides NRC regulatory guides are classified into the following divisions: 1. 2. 3. 4. 5. 6. 7. 8. 9. 10.
Power reactors Research and test reactors Fuels and materials facilities Environmental and siting Materials and plant protection Products Transportation Occupational health Antitrust and financial review General.
MISC, OTHER REFERENCES American Nuclear Society, 1984. Source terms. Special committee report. American Physical Society, 1985. Radionuclide release from severe accident management implementation. Study group report. ANS, 1983. Nuclear safety criteria for the design of stationary PWR plants. ANSI/ANS 51.1. Bayliss, C., Langley, K., 2003. Nuclear Decommissioning, Waste Management and Environmental Site Remediation. Elsevier, Oxford. Beckjord, E.S., 1995. NRC Research: A Ten-Year Vision. USNRC, Washington D.C. Bourgeois, J., Tanguy, P., Cogn´e, F., Petit, J., 1996. La suret´e nucleaire en France et dans le monde. Polytechnica, Paris. Broughton, J.M., Kuan, P., Petti, D.A., Tolman, E.L., 1989. A Scenario of the Three Mile Island Unit 2 Accident. Nuclear Technology 87 (1). Crede, C.E., 1976. Shock and Vibration Concepts in Engineering Design. Prentice-Hall, New York, USA. CSNI, 1990. Inadequate isolation of containment openings and penetrations. OECD/NEA Report 179. Cumo, M., Tripputi, I., Spezia, U., 2002. Decommissioning of nuclear plants, Scuola di specializzazion e in sicurezza nucleare ed industriale, Universita` di Roma. Etherington, H. (Ed.), 1958. Nuclear Engineering Handbook. McGraw-Hill, New York, USA. Forasassi, G., Guerrini, B., Petrangeli, G., 1997. Comparison of some passive safety concepts in nuclear and process industry systems. Post-SMIRT 14 International Seminar 18 Passive Safety Features in Nuclear Installations, 25 7 August, Pisa. Ford, D., 1982. The Cult of the Atom. Simon and Shuster, New York. Gittus, J., 1982. Power degraded core analysis. ND-R-610(S), United Kingdom Atomic Energy Authority. Glasstone, S., 1963. Nuclear Reactor Engineering. Van Nostrand, New York, USA. Hampton, W., 2001. Meltdown, A Race Against Nuclear Disaster at Three Mile Island, A Reporter’s Story. Candlewick Press, Cambridge, MA. Harbison, S., Martin, A., An introduction to radiation protection. ISBN 0412631105. Institute of Mechanical Engineers, 1988. Assuring it’s safe. ISBN 1860581471. Ishack, G., 1993. Operating experience with motor-operated valves: extracting the lessons learned from the Incident Reporting System. Report PWG1/OECD/NEA/CSNI.
ADDITIONAL REFERENCES
333
JGA, 1991. Recommended Practice for LNG Above-Ground Storage. Japanese Gas Association, Tokyo, Japan. Kletz, T., 1996. Dispelling Chemical Engineering Myths. Taylor & Francis, Oxford, UK. Lamarsh, J.R., Baratta, A., 2001. Introduction to Nuclear Engineering. Prentice Hall, NJ, USA. Lees, F.P., 2012. Loss Prevention in the Process Industries, vol. 3. Butterworth-Heinemann, Oxford. Lewis, E.E., Nuclear Power Reactor Safety. ISBN 0471533351. Mark’s Mechanical Engineers Handbook. 2006. McGraw-Hill, NY. Mazuzan, G.T., Walker, J.S., 1984. Controlling the Atom, the Beginning of Nuclear Regulation 1946 1962. University of California Press, Oakland, USA. Newmark, N.M., 1965. Effects of earthquakes on dams and embankments. Geotechnique 15 (2), 139 159. OECD, 1996. State of the art report on key fracture mechanics aspects of integrity assessment. OECD/GD (96) 6, NEA/CSNI/R(95)1. OECD, 2000. Report of the Senior Group on Safety Research. OECD/NEA/CSNI. Pearson, G.H., 1953. The Design of Valves and Fittings. Pittman and Sons, London. Petrangeli, G., 1987. Il concetto di rischio e definizione dei rischi. ANIAI, Rome. Petrangeli, G., Tononi, R., d’Auria, F., Mazzim, M., 1993. The SSN: an emergency system based on intentional coolant depressurization for PWRs. Nucl. Eng. Design 143, 25 54. Ramsey, C.B., Modarras, M., 1988. Commercial Nuclear Power, Assuring Safety for the Future. John Wiley & Sons, Hoboken, USA. Ravindra, M.K., 1992. Seismic assessment of chemical facilities under Califonia risk management and prevention program, International conference on Hazard Identification and Risk Analysis. Human Factors and Human Reliability in Process Safety, Orlando, FL, January. Robbins, A., 1991. Radioactive Heaven and Earth. The Apex Press, New York. Schweitzer, P.A., 1972. Handbook of Valves. Ind. Press, New York. Shibata, H., 1975. Anti-earthquake design of industrial facilities. Technocrat, 8 (11), 12 pages. Skousen P.L., 2004. Valve Handbook, Mc Graw Hill, NY. Stevenson, et al., 1992. Advances in the analysis and design of concrete structures, metal containment and liner plates for extreme loads. Nucl. Eng. Design 134, 12 pages. The Great Alaska Earthquake of 1964. 1972. National Academy of Sciences, Washington D.C. USA. Thompson, J., Beckerley, J.G., 1973. The Technology of Nuclear Reactor Safety. The MIT Press. USNRC, 1980. Equipment response at the El Centro steamplant during the 15 October 1979 Imperial Valley earthquake, NUREG/CR-1665. USNRC, 1985. Reliability analysis of containment isolation systems. NUREG CR-4220. USNRC, 1988. Technical findings and regulatory analysis for generic safety issue II.E.4.3 Containment integrity check. NUREG 1273. USNRC, 1990. Results of the public workshops. Supplement 1 to generic letter 89-10. USNRC, 1994. Information on schedule and grouping, and staff responses to additional public questions. Supplement 6 to generic letter 89-10. USNRC, 1996. Consideration of valve mispositioning in PWRs. Supplement 7 to generic letter 89-10. Voronin, L.M., et al., 1994. Safety of nuclear power plants (Russian edition, derived from the French book Memento de la suret´e nucleaire en exploitation). EDF-EPN-DSN-Paris-ISBN n2-7240-0090-0, September. Walker, J.S., 1992. Containing the Atom, Nuclear Regulation in a Changing Environment 1963 1971. University of California Press, Oakland, CA, USA. Walker, J.S., 2000. Permissible Dose, A History of Radiation Protection in the Twentieth Century. University of California Press, Oakland, CA, USA. Walker, J.S., 2004. Three Mile Island, A Nuclear Crisis in Historical Perspective. University of California Press, Oakland, CA, USA.
Essential references specifically related to each chapter of this book have been listed at the end of each chapter. However, these addresses for additional references give the reader a wider choice of documents. The references are grouped as follows: IAEA OECD NRC MISC
International Atomic Energy Agency (www.iaea.org) Organization for Economic Cooperation and Development (www.oecd.org/bookshop) United States Nuclear Regulatory Commission (www.nrc.gov) For references of other sources
IAEA REFERENCES NUCLEAR SAFETY STANDARDS SERIES Safety fundamentals: •
•
•
General safety requirements • Government, legal, and regulatory framework for safety • Leadership and management for safety • Radiation protection and safety of radiation sources • Safety assessment for facilities and activities • Predisposal management of radioactive waste • Decommissioning and termination of activities • Emergency preparedness and response Specific safety requirements • Site evaluation for nuclear installations • Safety of nuclear power plants Design Commissioning and operation • Safety of research reactors • Safety of nuclear fuel cycle facilities • Safety of radioactive waste disposal facilities • Safe transport of radioactive material Collection of safety guides Technical documents TECDOCS INSAG Accidents OECD references
331
332
ADDITIONAL REFERENCES
USNRC references Regulatory Guides NRC regulatory guides are classified into the following divisions: 1. 2. 3. 4. 5. 6. 7. 8. 9. 10.
Power reactors Research and test reactors Fuels and materials facilities Environmental and siting Materials and plant protection Products Transportation Occupational health Antitrust and financial review General.
MISC, OTHER REFERENCES American Nuclear Society, 1984. Source terms. Special committee report. American Physical Society, 1985. Radionuclide release from severe accident management implementation. Study group report. ANS, 1983. Nuclear safety criteria for the design of stationary PWR plants. ANSI/ANS 51.1. Bayliss, C., Langley, K., 2003. Nuclear Decommissioning, Waste Management and Environmental Site Remediation. Elsevier, Oxford. Beckjord, E.S., 1995. NRC Research: A Ten-Year Vision. USNRC, Washington D.C. Bourgeois, J., Tanguy, P., Cogn´e, F., Petit, J., 1996. La suret´e nucleaire en France et dans le monde. Polytechnica, Paris. Broughton, J.M., Kuan, P., Petti, D.A., Tolman, E.L., 1989. A Scenario of the Three Mile Island Unit 2 Accident. Nuclear Technology 87 (1). Crede, C.E., 1976. Shock and Vibration Concepts in Engineering Design. Prentice-Hall, New York, USA. CSNI, 1990. Inadequate isolation of containment openings and penetrations. OECD/NEA Report 179. Cumo, M., Tripputi, I., Spezia, U., 2002. Decommissioning of nuclear plants, Scuola di specializzazion e in sicurezza nucleare ed industriale, Universita` di Roma. Etherington, H. (Ed.), 1958. Nuclear Engineering Handbook. McGraw-Hill, New York, USA. Forasassi, G., Guerrini, B., Petrangeli, G., 1997. Comparison of some passive safety concepts in nuclear and process industry systems. Post-SMIRT 14 International Seminar 18 Passive Safety Features in Nuclear Installations, 25 7 August, Pisa. Ford, D., 1982. The Cult of the Atom. Simon and Shuster, New York. Gittus, J., 1982. Power degraded core analysis. ND-R-610(S), United Kingdom Atomic Energy Authority. Glasstone, S., 1963. Nuclear Reactor Engineering. Van Nostrand, New York, USA. Hampton, W., 2001. Meltdown, A Race Against Nuclear Disaster at Three Mile Island, A Reporter’s Story. Candlewick Press, Cambridge, MA. Harbison, S., Martin, A., An introduction to radiation protection. ISBN 0412631105. Institute of Mechanical Engineers, 1988. Assuring it’s safe. ISBN 1860581471. Ishack, G., 1993. Operating experience with motor-operated valves: extracting the lessons learned from the Incident Reporting System. Report PWG1/OECD/NEA/CSNI.
ADDITIONAL REFERENCES
333
JGA, 1991. Recommended Practice for LNG Above-Ground Storage. Japanese Gas Association, Tokyo, Japan. Kletz, T., 1996. Dispelling Chemical Engineering Myths. Taylor & Francis, Oxford, UK. Lamarsh, J.R., Baratta, A., 2001. Introduction to Nuclear Engineering. Prentice Hall, NJ, USA. Lees, F.P., 2012. Loss Prevention in the Process Industries, vol. 3. Butterworth-Heinemann, Oxford. Lewis, E.E., Nuclear Power Reactor Safety. ISBN 0471533351. Mark’s Mechanical Engineers Handbook. 2006. McGraw-Hill, NY. Mazuzan, G.T., Walker, J.S., 1984. Controlling the Atom, the Beginning of Nuclear Regulation 1946 1962. University of California Press, Oakland, USA. Newmark, N.M., 1965. Effects of earthquakes on dams and embankments. Geotechnique 15 (2), 139 159. OECD, 1996. State of the art report on key fracture mechanics aspects of integrity assessment. OECD/GD (96) 6, NEA/CSNI/R(95)1. OECD, 2000. Report of the Senior Group on Safety Research. OECD/NEA/CSNI. Pearson, G.H., 1953. The Design of Valves and Fittings. Pittman and Sons, London. Petrangeli, G., 1987. Il concetto di rischio e definizione dei rischi. ANIAI, Rome. Petrangeli, G., Tononi, R., d’Auria, F., Mazzim, M., 1993. The SSN: an emergency system based on intentional coolant depressurization for PWRs. Nucl. Eng. Design 143, 25 54. Ramsey, C.B., Modarras, M., 1988. Commercial Nuclear Power, Assuring Safety for the Future. John Wiley & Sons, Hoboken, USA. Ravindra, M.K., 1992. Seismic assessment of chemical facilities under Califonia risk management and prevention program, International conference on Hazard Identification and Risk Analysis. Human Factors and Human Reliability in Process Safety, Orlando, FL, January. Robbins, A., 1991. Radioactive Heaven and Earth. The Apex Press, New York. Schweitzer, P.A., 1972. Handbook of Valves. Ind. Press, New York. Shibata, H., 1975. Anti-earthquake design of industrial facilities. Technocrat, 8 (11), 12 pages. Skousen P.L., 2004. Valve Handbook, Mc Graw Hill, NY. Stevenson, et al., 1992. Advances in the analysis and design of concrete structures, metal containment and liner plates for extreme loads. Nucl. Eng. Design 134, 12 pages. The Great Alaska Earthquake of 1964. 1972. National Academy of Sciences, Washington D.C. USA. Thompson, J., Beckerley, J.G., 1973. The Technology of Nuclear Reactor Safety. The MIT Press. USNRC, 1980. Equipment response at the El Centro steamplant during the 15 October 1979 Imperial Valley earthquake, NUREG/CR-1665. USNRC, 1985. Reliability analysis of containment isolation systems. NUREG CR-4220. USNRC, 1988. Technical findings and regulatory analysis for generic safety issue II.E.4.3 Containment integrity check. NUREG 1273. USNRC, 1990. Results of the public workshops. Supplement 1 to generic letter 89-10. USNRC, 1994. Information on schedule and grouping, and staff responses to additional public questions. Supplement 6 to generic letter 89-10. USNRC, 1996. Consideration of valve mispositioning in PWRs. Supplement 7 to generic letter 89-10. Voronin, L.M., et al., 1994. Safety of nuclear power plants (Russian edition, derived from the French book Memento de la suret´e nucleaire en exploitation). EDF-EPN-DSN-Paris-ISBN n2-7240-0090-0, September. Walker, J.S., 1992. Containing the Atom, Nuclear Regulation in a Changing Environment 1963 1971. University of California Press, Oakland, CA, USA. Walker, J.S., 2000. Permissible Dose, A History of Radiation Protection in the Twentieth Century. University of California Press, Oakland, CA, USA. Walker, J.S., 2004. Three Mile Island, A Nuclear Crisis in Historical Perspective. University of California Press, Oakland, CA, USA.