Добірка наукової літератури з теми "Nucleate boiling degradation"
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Статті в журналах з теми "Nucleate boiling degradation"
Xia, Da-Hai, Bing Zhou, Jianqiu Wang, Zhiming Gao, Jihui Wang, Jing-Li Luo, and Chen Shen. "Passivation degradation of Alloy 800 on nucleate boiling surface." Corrosion Engineering, Science and Technology 52, no. 5 (March 30, 2017): 391–96. http://dx.doi.org/10.1080/1478422x.2017.1306991.
Повний текст джерелаWare, A. G., and V. N. Shah. "Age-related degradation of boiling water reactor vessel internals." Nuclear Engineering and Design 133, no. 1 (February 1992): 49–62. http://dx.doi.org/10.1016/0029-5493(92)90088-d.
Повний текст джерелаPshenichnikov, Anton, Saishun Yamazaki, David Bottomley, Yuji Nagae, and Masaki Kurata. "Features of a control blade degradation observed in situ during severe accident conditions in boiling water reactors." Journal of Nuclear Science and Technology 56, no. 5 (March 20, 2019): 440–53. http://dx.doi.org/10.1080/00223131.2019.1592724.
Повний текст джерелаXi, Mengmeng, Rong Cai, Xiao Chu, Fan Yang, Xu Ran, Zhifang Qiu, Jian Deng, and Wenxi Tian. "Theoretical Study on the Characteristics of Critical Heat Flux in Rectangular Channel of Natural Circulation under Motion Conditions." Science and Technology of Nuclear Installations 2020 (September 2, 2020): 1–18. http://dx.doi.org/10.1155/2020/9390645.
Повний текст джерелаGalushin, Sergey, and Pavel Kudinov. "Analysis of the Effect of Severe Accident Scenario on Debris Properties in Lower Plenum of Nordic BWR Using Different Versions of MELCOR Code." Science and Technology of Nuclear Installations 2019 (April 17, 2019): 1–18. http://dx.doi.org/10.1155/2019/5310808.
Повний текст джерелаPshenichnikov, Anton, Masaki Kurata, David Bottomley, Ikken Sato, Yuji Nagae, and Saishun Yamazaki. "New research programme of JAEA/CLADS to reduce the knowledge gaps revealed after an accident at Fukushima-1: introduction of boiling water reactor mock-up assembly degradation test programme." Journal of Nuclear Science and Technology 57, no. 4 (November 18, 2019): 370–79. http://dx.doi.org/10.1080/00223131.2019.1691070.
Повний текст джерелаDhir, Vijay K. "Advances in Understanding of Pool Boiling Heat Transfer—From Earth on to Deep Space." Journal of Heat Transfer 141, no. 5 (April 15, 2019). http://dx.doi.org/10.1115/1.4043282.
Повний текст джерелаManglik, R. M., and A. D. Athavale. "Pseudoplasticity and Dynamic Interfacial Tension Relaxation Effects on Nucleate Pool Boiling in Aqueous Polymeric Liquids." Journal of Heat Transfer 141, no. 5 (March 27, 2019). http://dx.doi.org/10.1115/1.4042699.
Повний текст джерелаYamashita, Takuya, Hiroshi Madokoro, and Ikken Sato. "Post-test Analyses of the CMMR-4 Test." Journal of Nuclear Engineering and Radiation Science, June 11, 2021. http://dx.doi.org/10.1115/1.4051443.
Повний текст джерелаКниги з теми "Nucleate boiling degradation"
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.
Знайти повний текст джерелаU.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.
Знайти повний текст джерелаU.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.
Знайти повний текст джерелаK, Samanta P., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Brookhaven National Laboratory, eds. Applications of reliability degradation analysis. Washington, DC: Division [of] Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996.
Знайти повний текст джерелаK, Samanta P., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Brookhaven National Laboratory, eds. Applications of reliability degradation analysis. Washington, DC: Division [of] Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996.
Знайти повний текст джерелаЧастини книг з теми "Nucleate boiling degradation"
Bahn, C. B., I. S. Hwang, I. H. Rhee, U. C. Kim, and J. W. Na. "Experimental Simulation of Boiling Crevice Chemistry." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 536–43. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch56.
Повний текст джерелаGordon, Barry, and Susan Garcia. "Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2061–76. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch213.
Повний текст джерелаYeh, Tsung-Kuang, Ching Chang, Fang Chu, and Chia-Shen Huang. "The Predicted Effectiveness of Noble Metal Treatment at the Chinshan Boiling Water Reactor." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1211–24. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch128.
Повний текст джерелаHeldt, J., and H. P. Seifert. "Stress Corrosion Cracking of Reactor Pressure Vessel Steels Under Boiling Water Reactor Conditions." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 901–10. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch95.
Повний текст джерелаYeh, Tsung-Kuang, and Mei-Ya Wang. "Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor during Startup Operations." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2079–89. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch215.
Повний текст джерелаGordon, Barry, and Susan Garcia. "Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 2061–77. Cham: Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_123.
Повний текст джерелаGibbs, J. P., R. G. Ballinger, J. H. Jackson, D. Isheim, and H. Hänninen. "Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Boiling Water Reactor Environments." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 745–60. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch78.
Повний текст джерелаCowan, Robert L., Juan Varela, and Susan E. Garcia. "The Effect of On-Line Noble Metal Addition on the Shut down Dose Rates of Boiling Water Reactors." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2023–36. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch210.
Повний текст джерелаYeh, Tsung-Kuang, and Mei-Ya Wang. "Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor During Startup Operations." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 2079–89. Cham: Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_124.
Повний текст джерелаGibbs, J. P., R. G. Ballinger, J. H. Jackson, D. Isheim, and H. Hänninen. "Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Boiling Water Reactor Environments." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 745–62. Cham: Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_47.
Повний текст джерелаТези доповідей конференцій з теми "Nucleate boiling degradation"
Kedzierski, M. A. "Effect of Al2O3 Nanolubricant on a Turbo-BII R134a Pool Boiling Surface." In ASME 2012 Third International Conference on Micro/Nanoscale Heat and Mass Transfer. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/mnhmt2012-75024.
Повний текст джерелаGraham, Jacob, Angelo Hawa, and Patricia Weisensee. "Evolution of Heat Transfer in Pool Boiling in Contaminated Water." In ASME 2020 18th International Conference on Nanochannels, Microchannels, and Minichannels collocated with the ASME 2020 Heat Transfer Summer Conference and the ASME 2020 Fluids Engineering Division Summer Meeting. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icnmm2020-1041.
Повний текст джерелаMoreno, Gilbert, Steven J. Oldenburg, Seung M. You, and Joo H. Kim. "Pool Boiling Heat Transfer of Alumina-Water, Zinc Oxide-Water and Alumina-Water+Ethylene Glycol Nanofluids." In ASME 2005 Summer Heat Transfer Conference collocated with the ASME 2005 Pacific Rim Technical Conference and Exhibition on Integration and Packaging of MEMS, NEMS, and Electronic Systems. ASMEDC, 2005. http://dx.doi.org/10.1115/ht2005-72375.
Повний текст джерелаGeisler, Karl J. L., and Avram Bar-Cohen. "Surface Effects on Confinement-Driven Pool Boiling Enhancement in Vertical Parallel-Plate Channels." In ASME 2005 Summer Heat Transfer Conference collocated with the ASME 2005 Pacific Rim Technical Conference and Exhibition on Integration and Packaging of MEMS, NEMS, and Electronic Systems. ASMEDC, 2005. http://dx.doi.org/10.1115/ht2005-72666.
Повний текст джерелаOkawa, Tsuyoshi, and Naoyuki Yomori. "Sensitivity Degradation Characteristics of Incore Neutron Detector for Heavy Water Reactor, Fugen NPP." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22234.
Повний текст джерелаKiss, E. "Component Reliability Considerations for New Designs and Extended Operation of Boiling Water Reactor (BWRs)." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48864.
Повний текст джерелаLi, Yongkui, Yoshiyuki Kaji, and Takahiro Igarashi. "Study of Weld Residual Stress Field in the Girth Seam H6A of Core Shroud of Boiling Water Reactor." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29269.
Повний текст джерелаWu, Wen, and Barclay G. Jones. "Simulation of Bubble Dynamics in Sub-Cooled Boiling on Fuel Clad in PWRs." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22682.
Повний текст джерелаDamerell, Paul S., and Todd A. Spears. "The Joint Owners’ Group Program on MOV Periodic Verification." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22599.
Повний текст джерелаKojima, Nobuo, Koji Nishino, Keisuke Sakemura, and Kengo Kobayashi. "The Solenoid Valve for Main Steam Relief Valve Adapted Under Severe Accident." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16030.
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