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Books on the topic 'Water cooled reactors'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 August 2024

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1

Oka, Yoshiaki. Super light water reactors and super fast reactors: Supercritical-pressure light water cooled reactor. Springer, 2010.

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2

Mori, Hideo, and Yoshiaki Oka. Supercritical-pressure light water cooled reactors. Springer, 2014.

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3

Oka, Yoshiaki, and Hideo Mori, eds. Supercritical-Pressure Light Water Cooled Reactors. Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-55025-9.

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4

Sapra, M. K. Design, development, and testing of 25 NB size accumulator isolation passive value (AIPV) for advanced heavy water reactor (AHWR). Bhabha Atomic Research Centre, 2010.

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5

Ross, W. E. CATHENA model of shield circuit ITER. CFFTP, 1992.

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6

Ross, W. E. Thermosyphoning analysis with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactor design. CFFTP, 1994.

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7

Ross, W. E. Analysis of loss of electrical power with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactordesign. CFFTP, 1994.

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8

J, Elliot A., and International Conference on Water Chemistry of Nuclear Reactor Systems. (6th : 1992 : Bournemouth, England)., eds. The temperature dependence of G-values for aqueous solutions irradiated with a 23 MeV 2H+ beam. System Chemistry & Corrosion Branch, Chalk River Laboratories, 1992.

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9

Kveton, O. K. ITER ISS system alternative specification study revision 1.0. Canadian Fusion Fuels Technology Project, 1990.

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10

Ross, W. E. Modified Cathena Model of a Shield Circuit for ITER. CFFTP, 1993.

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11

Kveton, O. K. ITER cooling system: Analysis of heat transfer media, operation and safety of cooling loop and blanket during conditioning and baking. Ontario Hydro, 1990.

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12

A, Allsop H., and International Conference on Water Chemistry of Nuclear Reactor Systems. (6th : 1992 : Bournemouth, England)., eds. The effect of dissolved oxygen in lithiated coolant. System Chemistry and Corrosion Branch, Chalk River Laboratories, 1992.

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13

Agency, International Atomic Energy, ed. Review of fuel failures in water cooled reactors. International Atomic Energy Agency, 1998.

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14

Agency, International Atomic Energy, ed. Water reactor fuel extended burnup study. International Atomic Energy Agency, 1992.

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15

Lee, D. T. Conceptual design of SEAFP tokamak/fuel cycle building-emergency detritiation and dust removal systems. Canadian Fusion Fuels Technology Project, 1994.

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16

Arkadov, G. V. Vibroshumovai Ła diagnostika VVE R. E nergoatomizdat, 2004.

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17

Teigensoku Supekutoru-ro ni Kansuru Kenkyūkai (4th 2001 Nihon Genshiryoku Kenkyūjo Tōkai Kenkyūjo). Dai 4-kai Teigensoku Supekutoru-ro ni Kansuru Kenkyūkai hōkokusho: 2001-nen 3-gatsu 2-nichi, Tōkai Kenkyūjo, Tōkai-mura. Nihon Genshiryoku Kenkyūjo, 2001.

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18

Vasilʹevich, Lysenko Vilen, ред. Opredelenie i͡a︡derno-fizicheskikh i teplofizicheskikh kharakteristik VVĖR s pomoshchʹi͡u︡ radiat͡s︡ionnykh izmeriteleĭ. Ėnergoatomizdat, 1985.

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19

Kikō, Genshiryoku Anzen Kiban. APWR chūseishi hanshatai no reikyakusei hyōka. Genshiryoku Anzen Kiban Kikō, 2005.

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20

Agency, International Atomic Energy, ed. Coolant technology of water cooled reactors: An overview. International Atomic Energy Agency, 1993.

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21

Stubley, P. SEAFP cooling system design: Task M8 - water coolant option (final report). CFFTP, 1994.

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22

Kikō, Genshiryoku Anzen Kiban. APWR no daihadan LOCA kaiseki no kentō. Genshiryoku Anzen Kiban Kikō, 2005.

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23

S, Rohatgi Upendra, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., and Brookhaven National Laboratory, eds. Preliminary phenomena identification and ranking tables (PIRT) for SBWR start-up stability. Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.

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24

Water, Chemistry and Materials Performance Conference (1986 Toronto Ont ). Proceedings of the Water Chemistry and Materials Performance Conference, October 21, 1986, King Edward Hotel, Toronto, Canada. Canadian Nuclear Society, 1986.

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25

Burrill, K. A. Deposition of corrosion products in-core. System Chemistry & Corrosion Branch, Chalk River Laboratories, 1994.

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26

Shii͡anov, A. I. Sistemy upravlenii͡a peregruzochnykh manipuli͡atorov AĖS s VVĖR. Ėnergoatomizdat, 1987.

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27

Samoĭlov, O. B. Bezopasnostʹ reaktorov VVR: Avarii͡a︡ s potereĭ teplonositeli͡a︡ : uchebnoe posobie dli͡a︡ studentov spet͡s︡ialʹnosteĭ 0310, 0311. Gorʹkovskiĭ politekhnicheskiĭ in-t im. A.A. Zhdanova, 1986.

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28

International, Symposium on Improvements in Water Reactor Fuel Technology and Utilization (1986 Stockholm Sweden). Improvements in water reactor fuel technology and utilization: Proceedings of an International Symposium on Improvements in Water Reactor Fuel Technology and Utilization. International Atomic Energy Agency, 1987.

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29

U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness. and Los Alamos National Laboratory, eds. TRAC-M/F77, version 5.5: Developmental assessment manual. Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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30

M, Straka, Ward L. W, Los Alamos National Laboratory, SCIENTECH Inc, ISL Inc, and U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., eds. TRAC-M validation test matrix. Division of System Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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31

M, Straka, Ward L. W, U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., and Los Alamos National Laboratory, eds. TRAC-M validation test matrix. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2001.

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32

G, Steinke R., U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., and Los Alamos National Laboratory, eds. TRAC-M/FORTRAN 90 (version 3.0) user manual. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2001.

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33

Zverkov, V. V. I͡A︡dernai͡a︡ paroproizvodi͡a︡shchai͡a︡ ustanovka s VVĖR-440. Ėnergoatomizdat, 1987.

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34

M, Straka, Ward L. W, Los Alamos National Laboratory, SCIENTECH Inc, ISL Inc, and U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., eds. TRAC-M validation test matrix. Division of System Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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35

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. and Science and Engineering Associates, eds. Drywell debris transport study: Final report. Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

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36

U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution, ed. Regulatory analysis for the resolution of generic safety issue 105: Interfacing system loss-of-coolant accident in light-water reactors. Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

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37

Agency, International Atomic Energy, ed. Review of fuel element developments for water cooled nuclear power reactors. International Atomic Energy Agency, 1989.

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38

Steinke, R. G. TRAC-M programmer's guide: Fortran 77, version 5.5. Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

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39

W, Spore J., U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., and Los Alamos National Laboratory, eds. TRAC-M/FORTRAN 90 (version 3.0) theory manual. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2001.

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40

J, Jolly-Woodruff S., Spore J. W, U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., and Los Alamos National Laboratory, eds. TRAC-M programmer's guide: Fortran 77, version 5.5. Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

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41

Steinke, R. G. TRAC-M programmer's guide: Fortran 77, version 5.5. U.S. Nuclear Regulatory Commission, 1999.

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42

J, Jolly-Woodruff S., Spore J. W, U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., and Los Alamos National Laboratory, eds. TRAC-M programmer's guide: Fortran 77, version 5.5. Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

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43

I͡A︡, Chebotina M., and Akademii͡a︡ nauk SSSR. Uralʹskoe otdelenie., eds. Radioėkologicheskie issledovanii͡a︡ Beloi͡a︡rskogo vodokhranilishcha. Akademii͡a︡ nauk SSSR, Uralʹskoe otd-nie, 1992.

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44

Kiko, Genshiryoku Anzen Kiban. Heisei 22-nendo kōsokuro SG dennetsukan shōkibo mizu rōei jisho kaiseki kōdo SWINS-II no seibi. Genshiryoku Anzen Kiban Kiko, 2012.

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45

V, Rao D., Shaffer C, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Science and Engineering Associates, eds. Drywell debris transport study: Final report. U.S. Nuclear Regulatory Commission, 1999.

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46

H, Sanchez-Espinoza V., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, and Forschungszentrum Karlsruhe, eds. Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

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47

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

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48

Agency, International Atomic Energy, ed. Guidebook on destructive examination of water reactor fuel. International Atomic Energy Agency, 1997.

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49

Kikō, Genshiryoku Anzen Kiban. APWR puranto jiko kaiseki: Jōki hasseiki dennetsukan hason jiko. Genshiryoku Anzen Kiban Kikō, 2005.

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50

Gierszewski, Paul Joseph. Tritium supply for ITER from Ontario Hydro. Canadian Fusion Fuels Technology Project, 1996.

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