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1

Glasstone, Samuel. Nuclear Reactor Engineering: Reactor Systems Engineering. Boston, MA: Springer US, 1994.

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2

Zohuri, Bahman. Neutronic Analysis For Nuclear Reactor Systems. Cham: Springer International Publishing, 2019. http://dx.doi.org/10.1007/978-3-030-04906-5.

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3

Zohuri, Bahman. Neutronic Analysis For Nuclear Reactor Systems. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-42964-9.

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4

Myers, Lynne C. Nuclear power systems: Their safety. [Ottawa]: Library of Parliament, Research Branch, 1989.

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5

Myers, Lynne C. Nuclear power systems: Their safety. [Ottawa]: Library of Parliament, Research Branch, 1996.

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6

United States. National Aeronautics and Space Administration., red. Small space reactor power systems for unmanned solar system exploration missions. [Washington, D.C.]: National Areonautics and Space Administration, 1987.

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7

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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8

Jalel, N. A. Expert systems for fault diagnosis in nuclear reactor control. Sheffield: University of Sheffield, Dept. of Control Engineering, 1990.

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9

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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10

U.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors. i Lawrence Livermore National Laboratory, red. Reviewing real-time performance of nuclear reactor safety 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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11

Erich, Merz, Walter Carl E, North Atlantic Treaty Organization. Scientific Affairs Division. i NATO Advanced Research Workshop on Advanced Nuclear Systems Consuming Excess Plutonium (1996 : Moscow, Russia), red. Advanced nuclear systems consuming excess plutonium. Dordrecht: Kluwer Academic Publishers, 1997.

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12

United States. National Aeronautics and Space Administration., red. Small reactor power systems for manned planetary surface bases. [Washington, D.C.]: National Aeronautics and Space Administration, 1987.

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13

Griffith, P. Screening reactor steam/water piping systems for water hammer. Washington, DC: U.S. Nuclear Regulatory Commission, 1997.

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14

Astrin, Cal D. Startup control of the TOPAZ-II space nuclear reactor. Monterey, Calif: Naval Postgraduate School, 1996.

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15

International Atomic Energy Agency; IAEA. Reactor coolant and associated systems in nuclear power plants: A safety guide. Vienna: The Agency, 1986.

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16

D, Schrader, Yamamoto R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. i Lawrence Livermore National Laboratory, red. Review templates for computer-based reactor protection systems. Washington, DC: U.S. Nuclear Regulatory Commission, 2000.

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17

United States. National Aeronautics and Space Administration., red. Multi-reactor power system configurations for multimegawatt nuclear electric propulsion. [Washington, DC]: National Aeronautics and Space Administration, 1991.

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18

H, Wyman Robert, U.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors. i Lawrence Livermore National Laboratory, red. The programmable logic controller and its application in nuclear reactor 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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19

Katsman, David. Soviet nuclear power plants: Reactor types, water and chemical control systems, turbines. Falls Church, VA (7700 Leesburg Pike, #250, Falls Church 22043): Delphic Associates, 1986.

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20

International Symposium on Advanced Nuclear Power Systems: Design, Technology, Safety and Strategies for Their Deployment (1993 Seoul, Korea). Advanced nuclear power systems: Design, technology, safety and strategies for their deployment : proceedings of an International Symposium on Advanced Nuclear Power Systems: Design, Technology, Safety and Strategies for their Deployment. Vienna: International Atomic Energy Agency, 1994.

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21

L, Edson Jerald, Fineman C. F, Idaho National Engineering Laboratory i U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., red. Aging study of boiling water reactor high pressure injection systems. Washington, DC: U.S. Nuclear Regulatory Commission, 1995.

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22

Society, British Nuclear Energy, Institution of Chemical Engineers (Great Britain), Royal Society of Chemistry (Great Britain) i European Nuclear Society, red. Water chemistry of nuclear reactor systems 6: Proceedings of the international conference. London: British Nuclear Energy Society, 1992.

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23

Wheeler, T. A. Calculation of failure importance measures for basic events and plant systems in nuclear power plants. Washington, DC: Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.

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24

Wheeler, T. A. Calculation of failure importance measures for basic events and plant systems in nuclear power plants. Washington, DC: Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.

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25

U.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors. i Lawrence Livermore National Laboratory, red. Method for performing diversity and defense-in-depth analyses of reactor protection systems. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1994.

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26

United States. General Accounting Office., red. Nuclear science: Usefulness of space power research to ground-based nuclear reactor systems : report to congressional requesters. Washington, D.C: The Office, 1988.

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27

Agency, International Atomic Energy, red. Design of the reactor containment systems in nuclear power plants: A safety guide. Vienna: International Atomic Energy Agency, 1985.

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28

S, Bloomfield H., i United States. National Aeronautics and Space Administration., red. Comparison of solar photovoltaic and nuclear reactor power systems for a human-tended lunar observatory. [Washington, D.C.]: National Aeronautics and Space Administration, 1989.

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29

Nelson, William R. Response tree evaluation: Experimental assessment of an expert system for nuclear reactor operators. [Idaho Falls, Idaho]: EG&G Idaho, 1985.

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30

Wesley, D. A. Screening methods for developing internal pressure capacities for components in systems interfacing with nuclear power plant reactor coolant systems. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

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31

S, El-Genk Mohamed, Harper William B i United States. National Aeronautics and Space Administration., red. Closed Brayton cycle power system with a high temperature pellet bed reactor heat source for NEP applications. [Washington, DC: National Aeronautics and Space Administration, 1993.

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32

Meale, B. M. An aging failure survey of light water reactor safety systems and components. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

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33

International Conference and Technology Exposition on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options: Global '93 (1993 Seattle, Wash.). Proceedings of the International Conference and Technology Exposition on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options: Global '93. La Grange Park, Ill: American Nuclear Society, 1993.

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34

U.S. Nuclear Regulatory Commission., red. Screening Reactor Steam/Water Piping Systems For Water Hammer... Nureg/CR-6519... U.S. Nuclear Regulatory Commission... 1997. [S.l: s.n., 1997.

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35

United States. National Aeronautics and Space Administration., red. Evolving the SP-100 reactor in order to boost large payloads to GEO and to low lunar orbit via nuclear-electric propulsion. [Washington, DC]: National Aeronautics and Space Administration, 1991.

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36

United States. National Aeronautics and Space Administration., red. Evolving the SP-100 reactor in order to boost large payloads to GEO and to low lunar orbit via nuclear-electric propulsion. [Washington, DC]: National Aeronautics and Space Administration, 1991.

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37

United States. Office of the Assistant Secretary for Nuclear Energy, red. Impact of the use of low or medium enriched uranium on the masses of space nuclear reactor power systems. Washington, DC: The Office, 1994.

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38

National Heat Transfer Conference (29th 1993 Atlanta, Ga.). Transient phenomena in nuclear reactor systems: Presented at the 29th National Heat Transfer Conference, Atlanta, Georgia, August 8-11, 1993. New York: ASME, 1993.

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39

Germany) Bieleschweig Workshop on System Engineering (11th 2011 Bielefeld. The Fukushima Dai-Ichi accident. Wien: LIT, 2013.

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40

Cramond, Wallis R. Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor: Case study. Washington, DC: Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987.

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41

B, Cheung F., McAssey E. V, American Society of Mechanical Engineers. Heat Transfer Division. i International Mechanical Engineering Congress and Exposition (1994 : Chicago, Ill.), red. Natural circulation phenomena in nuclear reactor systems: Presented at 1994 International Mechanical Engineering Congress and Exposition, Chicago, Illinois, November 6-11, 1994. New York: American Society of Mechanical Engineers, 1994.

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42

Hoskins, Raymond E. Nuclear waste management systems issues related to transportation cask design: At-reactor spent fuel storage, monitored retrievable storage and modal mix. [Culver City]: State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office, 1990.

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43

Natesan, K. Knowledge base report on emergency core cooling sump performance in operating light water reactors. Washington, D.C: United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2014.

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44

Subcommittee, United States Congress House Committee on Armed Services Procurement and Military Nuclear Systems. P-Reactor operations at Savannah River: Hearing before the Procurement and Military Nuclear Systems Subcommittee of the Committee on Armed Services, House of Representatives, One Hundredth Congress, second session, September 28, 1988. Washington: U.S. G.P.O., 1988.

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45

Subcommittee, United States Congress House Committee on Armed Services Procurement and Military Nuclear Systems. P-Reactor operations at Savannah River: Hearing before the Procurement and Military Nuclear Systems Subcommittee of the Committee on Armed Services, House of Representatives, One Hundredth Congress, second session, September 28, 1988. Washington: U.S. G.P.O., 1988.

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46

Subcommittee, United States Congress House Committee on Armed Services Procurement and Military Nuclear Systems. P-Reactor operations at Savannah River: Hearing before the Procurement and Military Nuclear Systems Subcommittee of the Committee on Armed Services, House of Representatives, One Hundredth Congress, second session, September 28, 1988. Washington: U.S. G.P.O., 1988.

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47

Subcommittee, United States Congress House Committee on Armed Services Procurement and Military Nuclear Systems. P-Reactor operations at Savannah River: Hearing before the Procurement and Military Nuclear Systems Subcommittee of the Committee on Armed Services, House of Representatives, One Hundredth Congress, second session, September 28, 1988. Washington: U.S. G.P.O., 1988.

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48

Thomas, Jean-BaptisteVE, Pascal Anzieu i Richarch Lenain. Nuclear Reactor Systems. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-1985-0.

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49

Nuclear Reactor Engineering: Reactor Systems Engineering. Springer, 2011.

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50

Cacuci, D. G. Nuclear Reactor Safety Systems. Taylor & Francis Group, 2011.

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