Books on the topic 'Nucleate boiling'

Prabhu, K. Narayan, and Nikolai Kobasko, eds. Film and Nucleate Boiling Processes. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp1534-eb.

Bertsch, George M. Nucleate pool boiling characteristics of R-124. Monterey, Calif: Naval Postgraduate School, 1993.

Cieśliński, Janusz T. Modelowanie wrzenia pęcherzykowego. Gdańsk: Wydawn. Politechniki Gdańskiej, 2005.

Rule, T. D. Design, construction, and qualification of a microscale heater array for use in boiling heat transfer. [Cleveland, Ohio]: National Aeronautics and Space Administration, Lewis Research Center, 1998.

Engineering, Foundation Conference on Pool and External Flow Boiling (1992 Santa Barbara Calif ). Pool and external flow boiling: Proceedings of the Engineering Foundation Conference on Pool and External Flow Boiling, Santa Barbara, California, March 22-27, 1992. New York: Published on the behalf of the Engineering Foundation by The Society, 1992.

Baĭdakov, V. G. Explosive boiling of superheated cryogenic liquids. Weinheim: Wiley-VCH, 2007.

Dorofeev, B. M. Akustika kipenii︠a︡. 2nd ed. Stavropolʹ: Izd-vo Stavropolʹskogo gos. universiteta., 2007.

Lim, Y. H. Subcooled nucleate boiling in cooling channels for pressure die casting. Manchester: UMIST, 1996.

Prisni͡akov, V. F. Kipenie. Kiev: Nauk. dumka, 1988.

Chilman, Scott V. Nucleate boiling characteristics of R-113 in a small enhanced tube bundle. Monterey, Calif: Naval Postgraduate School, 1991.

L, Linne Diane, Rousar Donald C, and United States. National Aeronautics and Space Administration., eds. Forced convection boiling and critical heat flux of ethanol in electrically heated tube tests. [Cleveland, Ohio]: National Aeronautics and Space Administration, Lewis Research Center, 1998.

Bode, Andreas. Heat transfer, vapour bubble dynamics and sound emission in subcooled nucleate pool boiling. Aachen: Shaker Verlag, 2004.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. and Central Electricity Generating Board. Generation Development and Construction Division., eds. Assessment of subcooled boiling model used in RELAP5/MOD2 (cycle 36.05, version E03) against experimental data. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

Hsu, Yih-Yun. Transport processes in boiling and two-phase systems, including near-critical fluids. La Grange Park, Ill., USA: American Nuclear Society, 1986.

Haas, Russell E. Nucleate pool boiling of R-114/oil mixtures in a small enhanced tube bundle. Monterey, Calif: Naval Postgraduate School, 1992.

John, Benton, Kucner Robert, and NASA Glenn Research Center, eds. Subcooled pool boiling heat transfer mechanisms in microgravity: Terrier-improved orion sounding rocket experiment. [Cleveland, Ohio]: National Aeronautics and Space Administration, Glenn Research Center, 2000.

Lake, Lannie R. The influence of a lower heated tube on nucleate pool boiling from a horizontal tube. Monterey, Calif: Naval Postgraduate School, 1992.

Sugiyama, Dean C. Nucleate pool boiling of R-114 and R-114/oil mixtures from single enhanced tubes. Monterey, Calif: Naval Postgraduate School, 1991.

Reilly, James T. The influence of oil contamination on the nucleate pool-boiling behavior of R-114 from a structured surface: By James T. Reilly. Monterey, Calif: Naval Postgraduate School, 1985.

Akcasayar, Nezih. Nucleate pool boiling performance of finned and high flux tube bundles in R-114/oil mixtures. Monterey, Calif: Naval Postgraduate School, 1989.

Snyder, Trevor James. A study on the competing effects of the dielectrophoretic force and buoyancy on nucleate boiling heat transfer rates and an analogy with variable gravity boiling results. Pullman, WA: School of Mechanical and Materials Engineering, Washington State University, 1995.

Anderson, Carl Lee. Nucleate pool boiling performance of smooth and finned tube bundles in R-113 and R-114/oil mixtures. Monterey, Calif: Naval Postgraduate School, 1989.

Bierschbach, M. C. Estimating boiling water reactor decommissioning costs: A user's manual for the BWR cost estimating computer program (CECP) software : draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1994.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Regulatory Applications. and Pacific Northwest National Laboratory (U.S.), eds. Estimating boiling water reactor decommissioning costs: A user's manual for the BWR Cost Estimating Computer Program (CECP) software : final report. Washington, DC: Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commssion, 1996.

J, Moody F., ed. The thermal-hydraulics of a boiling water nuclear reactor. 2nd ed. La Grange Park, Ill., USA: American Nuclear Society, 1993.

(Bonn, Germany) Kerntechnische Gesellschaft. SWR 1000: Ein zukunftsweisendes Reaktorkonzept : Tagungsbericht = SWR 1000 : a reactor concept for the future : proceedings. Bonn: INFORUM, 1998.

Hawthorne, J. R. Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Shih, Chunkuan, and K. Tien. The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model. Washington, DC: U.S. Nuclear Regulatory Commission, Division of Systems Analysis, Office of Nuclear Regulatory Research, 2014.

Nikolaevich, Andreenko Sergeĭ, ed. Peregruzochnye mashiny kanalʹnykh i͡a︡dernykh ėnergeticheskikh reaktorov. Moskva: Ėnergoatomizdat, 1986.

Hawthorne, J. R. Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. and Oak Ridge National Laboratory, eds. Boiling-water reactor internals aging degradation study: Phase 1. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. and Oak Ridge National Laboratory, eds. Boiling-water reactor internals aging degradation study: Phase 1. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. and Oak Ridge National Laboratory, eds. Boiling-water reactor internals aging degradation study: Phase 1. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/4. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/6. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.

Gauntt, Randall Owen. The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

S, Rohatgi Upendra, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., and Brookhaven National Laboratory, eds. RAMONA-4B, a computer code with three-dimensional neutron kinetics for BWR and SBWR system transients. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/6. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/4. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.

Gauntt, Randall Owen. The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

U.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors, ed. Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1995.

J, García García, López Montero J. V, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., and NUCLENOR S. A, eds. Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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

U.S. Nuclear Regulatory Commission. Division of Human Factors Technology, ed. Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors. Washington, DC: Division of Human Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.

Kikō, Genshiryoku Anzen Kiban. BWR puranto tōkeiteki anzen hyōka shuhō no seibi: Futashikasa kaiseki kinō no kumikomi to jikki benchi māku mondai kaiseki : Heisei 21-nendo. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2010.

H, Yan, Theofanous T. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and University of California, Santa Barbara. Center for Risk Studies and Safety., eds. The management of ATWS by boron injection. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409. Washington, D.C: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1986.

Kikō, Genshiryoku Anzen Kiban. CCDP to CLERP o kōryoshita EPRI shuhō ni yoru BWR no RI-ISI shihyōka ni kansuru hōkokusho: Report on trial assessment of RI-ISI program by EPRI method for BWR evaluating CCDP and CLERP. Tōkyō-to Minato-ku: Dokuritsu Gyōsei Hōjin Genshiryoku Anzen Kiban Kikō, 2013.

H, Yan, Theofanous T. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and University of California, Santa Barbara. Center for Risk Studies and Safety., eds. The management of ATWS by boron injection. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

Kikō, Genshiryoku Anzen Kiban. Kairyōgata futtōsuigata keisuiro no kanensei gasu nōdo seigyokei ni kakaru seinō hyōka kaiseki hōkokusho. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2011.