Статті в журналах з теми "Nuclear reactor vessel"
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Zhou, Linjun, Jie Dai, Yang Li, Xin Dai, Changsheng Xie, Linze Li, and Liansheng Chen. "Research Progress of Steels for Nuclear Reactor Pressure Vessels." Materials 15, no. 24 (December 8, 2022): 8761. http://dx.doi.org/10.3390/ma15248761.
Повний текст джерелаKondylakis, J. S. "Theoretically and under very special applied conditions a nuclear fission reactor may explode as nuclear bomb." HNPS Proceedings 18 (November 23, 2019): 121. http://dx.doi.org/10.12681/hnps.2558.
Повний текст джерелаKantsedalov, V. G., V. P. Samoilenko, and A. T. Toporkov. "Remote checking of nuclear-reactor vessel pipes." Soviet Atomic Energy 62, no. 4 (April 1987): 326–29. http://dx.doi.org/10.1007/bf01123375.
Повний текст джерелаKramskoi, A. V., Y. G. Lyudmirsky, M. E. Zhidkov, and M. I. Kramskaia. "On extending the life of nuclear reactors." Journal of Physics: Conference Series 2131, no. 2 (December 1, 2021): 022030. http://dx.doi.org/10.1088/1742-6596/2131/2/022030.
Повний текст джерелаZabusov, Oleg O., Boris A. Gurovich, Evgenia A. Kuleshova, Michail A. Saltykov, Svetlana V. Fedotova, and Alexey P. Dementjev. "Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels." Key Engineering Materials 592-593 (November 2013): 577–81. http://dx.doi.org/10.4028/www.scientific.net/kem.592-593.577.
Повний текст джерелаDombrovskii, Leonid A., Vladimir N. Mineev, Anatolii S. Vlasov, Leonid I. Zaichik, Yuri A. Zeigarnik, Andrei B. Nedorezov, and Aleksandr S. Sidorov. "In-vessel corium catcher of a nuclear reactor." Nuclear Engineering and Design 237, no. 15-17 (September 2007): 1745–51. http://dx.doi.org/10.1016/j.nucengdes.2007.03.009.
Повний текст джерелаRosinski, S. T. "Nuclear reactor pressure vessel-specific flaw distribution development." Theoretical and Applied Fracture Mechanics 19, no. 2 (November 1993): 133–43. http://dx.doi.org/10.1016/0167-8442(93)90015-4.
Повний текст джерелаAzhagarason, B., N. Mahendran, Tarun Kumar Mitra, and Prabhat Kumar. "Technological Challenges in Manufacturing of over Dimensional Stainless Steel Components of PFBR." Advanced Materials Research 794 (September 2013): 186–93. http://dx.doi.org/10.4028/www.scientific.net/amr.794.186.
Повний текст джерелаPopov, V., V. Mileikovskyi, and O. O. Tryhub. "Expert express assessment of the impact of heat and mass transfer processes on the residual life of the WWER-1000 reactor vessel due to metal embrittlement." Ventilation, Illumination and Heat Gas Supply 41 (April 12, 2022): 39–49. http://dx.doi.org/10.32347/2409-2606.2022.41.39-49.
Повний текст джерелаMarcus, Gail H. "Nuclear Power after Fukushima." Mechanical Engineering 133, no. 12 (December 1, 2011): 27–29. http://dx.doi.org/10.1115/1.2011-dec-2.
Повний текст джерелаLangston, Lee S. "PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?" Mechanical Engineering 133, no. 08 (August 1, 2011): 54–59. http://dx.doi.org/10.1115/1.2011-aug-5.
Повний текст джерелаWen, Lijing, Chao Guo, Tieping Li, and Chunming Zhang. "Stress Analysis for Reactor Coolant Pump Nozzle of Nuclear Reactor Pressure Vessel." Journal of Applied Mathematics and Physics 01, no. 06 (2013): 62–64. http://dx.doi.org/10.4236/jamp.2013.16013.
Повний текст джерелаWeng, Yu, Haitao Wang, Benan Cai, Hongfang Gu, and Haijun Wang. "Flow mixing and heat transfer in nuclear reactor vessel with direct vessel injection." Applied Thermal Engineering 125 (October 2017): 617–32. http://dx.doi.org/10.1016/j.applthermaleng.2017.07.040.
Повний текст джерелаKuroda, Toshio, and Fukuhisa Matsuda. "Irradiation Embrittlement for Weldment of Nuclear Reactor Vessel Steel." Journal of the Japan Welding Society 65, no. 7 (1996): 568–75. http://dx.doi.org/10.2207/qjjws1943.65.7_568.
Повний текст джерелаBibel, George. "Significant wastage of a nuclear reactor pressure vessel head." International Journal of Forensic Engineering 2, no. 1 (2014): 1. http://dx.doi.org/10.1504/ijfe.2014.059243.
Повний текст джерелаHoriya, T., T. Takeda, and K. Yamato. "Study on Underclad Cracking in Nuclear Reactor Vessel Steels." Journal of Pressure Vessel Technology 107, no. 1 (February 1, 1985): 30–35. http://dx.doi.org/10.1115/1.3264400.
Повний текст джерелаvan Hoorebeke, L., J. van de Velde, D. Segers, L. Dorikens-Vanpraet, and S. Simula. "Positron Annihilation Measurements on Nuclear Reactor Pressure Vessel Steels." Le Journal de Physique IV 05, no. C1 (January 1995): C1–171—C1–175. http://dx.doi.org/10.1051/jp4:1995120.
Повний текст джерелаBose, M. R. S. C., G. Thomas, R. Palaninathan, S. P. Damodaran, and P. Chellapandi. "Buckling investigations on a nuclear reactor inner vessel model." Experimental Mechanics 41, no. 2 (June 2001): 144–50. http://dx.doi.org/10.1007/bf02323190.
Повний текст джерелаPetrov, Yu I., B. F. Balunov, S. S. Davydovand, and E. E. Pakh. "Fusion reactor vacuum vessel cooldown." Plasma Devices and Operations 8, no. 3 (December 2000): 167–77. http://dx.doi.org/10.1080/10519990008228762.
Повний текст джерелаKovbasenko, Yu, and Yevgen Bilodid. "Analysis of criticality of melt during severe accidents in reactor vessel." Nuclear and Radiation Safety, no. 2(78) (June 7, 2018): 3–10. http://dx.doi.org/10.32918/nrs.2018.2(78).01.
Повний текст джерелаTrampus, Péter. "Reactor Pressure Vessel Integrity in Light of the Evolution of Materials Science and Engineering." Materials Science Forum 473-474 (January 2005): 287–92. http://dx.doi.org/10.4028/www.scientific.net/msf.473-474.287.
Повний текст джерелаBakhracheva, Yulia S. "Influence of irradiation on the dynamics of changes in the mechanical properties of the nuclear reactor vessel." MATEC Web of Conferences 226 (2018): 01024. http://dx.doi.org/10.1051/matecconf/201822601024.
Повний текст джерелаKim, J. C., Jae Boong Choi, Yoon Suk Chang, Young Jin Kim, Youn Won Park, and Young Hwan Choi. "Development of Web-Based Fatigue Life Evaluation System for Reactor Pressure Vessel." Solid State Phenomena 120 (February 2007): 25–30. http://dx.doi.org/10.4028/www.scientific.net/ssp.120.25.
Повний текст джерелаIsnaini, Muhammad Darwis, Elfrida Saragi, and Veronika Indriati Sri Wardani. "PREDICTION OF AP1000’S NUCLEAR REACTOR PRESSURE VESSEL TEMPERATURE DURING NORMAL OPERATION." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 24, no. 3 (November 9, 2022): 99. http://dx.doi.org/10.17146/tdm.2022.24.3.6684.
Повний текст джерелаKim, Hwan Yeol, Sevostian Bechta, Jerzy Foit, and Seong Wan Hong. "In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor." Science and Technology of Nuclear Installations 2018 (October 2, 2018): 1–3. http://dx.doi.org/10.1155/2018/3918150.
Повний текст джерелаFejt, Filip. "THERMAL-HYDRAULIC ANALYSIS OF IRT-4M IN REACTIVITY INSERTION ACCIDENT AT VR-1 REACTOR." Acta Polytechnica CTU Proceedings 4 (December 16, 2016): 22. http://dx.doi.org/10.14311/ap.2016.4.0022.
Повний текст джерелаWeng, Yu, Haitao Wang, Haijun Wang, Jialun Liu, Jie Pan, and Zhian Deng. "The thermal-fluid-solid coupling effect in nuclear reactor vessel with direct vessel injection." Progress in Nuclear Energy 152 (October 2022): 104364. http://dx.doi.org/10.1016/j.pnucene.2022.104364.
Повний текст джерелаGémes, György András. "Effect of Cladding on the Reactor Pressure Vessel Safety." Materials Science Forum 537-538 (February 2007): 363–70. http://dx.doi.org/10.4028/www.scientific.net/msf.537-538.363.
Повний текст джерелаPospíšil, Petr. "Reactor Vessel Internals Segmentation Experience using Mechanical Cutting Tools." Technological Engineering 10, no. 2 (December 1, 2013): 6–10. http://dx.doi.org/10.2478/teen-2013-0012.
Повний текст джерелаNguyen, Huu Tiep, Viet Ha Pham Nhu, and Minh Tuan Nguyen. "Calculation of neutron and gamma fluences on VVER reactor pressure vessel." Nuclear Science and Technology 6, no. 4 (December 30, 2016): 18–25. http://dx.doi.org/10.53747/jnst.v6i4.172.
Повний текст джерелаVuiart, Romain, Mariya Brovchenko, Julien Taforeau, and Eric Dumonteil. "A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark." Energies 15, no. 14 (July 12, 2022): 5098. http://dx.doi.org/10.3390/en15145098.
Повний текст джерелаDorf, Valery A., and Boris K. Pergamenchik. "Updating of dry shielding of nuclear power plant reactor vessel." Vestnik MGSU, no. 4 (April 2021): 506–12. http://dx.doi.org/10.22227/1997-0935.2021.4.506-512.
Повний текст джерелаBernsen, Sidney, Bryan Erler, Dana K. Morton, and Owen Hedden. "The Code Builders." Mechanical Engineering 136, no. 05 (May 1, 2014): 36–41. http://dx.doi.org/10.1115/1.2014-may-2.
Повний текст джерелаNakata, Alexandre Ezzidi, Masanori Naitoh, and Chris Allison. "NEED OF A NEXT GENERATION SEVERE ACCIDENT CODE." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 21, no. 3 (November 12, 2019): 119. http://dx.doi.org/10.17146/tdm.2019.21.3.5630.
Повний текст джерелаNguyen, Huu Tiep, Viet Ha Pham Nhu, and Minh Tuan Nguyen. "Investigation of DPA in the reactor pressure vessel of VVER-1000/V320." Nuclear Science and Technology 7, no. 4 (September 1, 2021): 16–25. http://dx.doi.org/10.53747/jnst.v7i4.93.
Повний текст джерелаPark, Sang-Hyun, Kwang-Hyun Bang, and Jong-Rae Cho. "Structural Integrity Evaluation of a Reactor Cavity during a Steam Explosion for External Reactor Vessel Cooling." Energies 14, no. 12 (June 17, 2021): 3605. http://dx.doi.org/10.3390/en14123605.
Повний текст джерелаShiga, Tomoya, Yudai Tanaka, and Tetsuaki Takada. "Process of Air Ingress during a Depressurization Accident of GTHTR300." Science and Technology of Nuclear Installations 2018 (September 2, 2018): 1–15. http://dx.doi.org/10.1155/2018/6378504.
Повний текст джерелаLangston, Lee S. "Pebbles Making Waves." Mechanical Engineering 130, no. 02 (February 1, 2008): 34–38. http://dx.doi.org/10.1115/1.2008-feb-3.
Повний текст джерелаYahr, G. T. "Fatigue Design Curves for 6061-T6 Aluminum." Journal of Pressure Vessel Technology 119, no. 2 (May 1, 1997): 211–15. http://dx.doi.org/10.1115/1.2842286.
Повний текст джерелаPark, Rae-Joon, Jae Ryong Lee, Kwang Soon Ha, and Hwan Yeol Kim. "Evaluation of in-vessel corium retention through external reactor vessel cooling for small integral reactor." Nuclear Engineering and Design 262 (September 2013): 571–78. http://dx.doi.org/10.1016/j.nucengdes.2013.06.003.
Повний текст джерелаAra, K., N. Ebine, and N. Nakajima. "A New Method of Nondestructive Measurement for Assessment of Material Degradation of Aged Reactor Pressure Vessels." Journal of Pressure Vessel Technology 118, no. 4 (November 1, 1996): 447–53. http://dx.doi.org/10.1115/1.2842212.
Повний текст джерелаRodríguez-Prieto, Alvaro, Manuel Callejas, Ernesto Primera, Guglielmo Lomonaco, and Ana María Camacho. "Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels." Mathematics 10, no. 10 (May 23, 2022): 1779. http://dx.doi.org/10.3390/math10101779.
Повний текст джерелаYang, J., M. B. Dizon, F. B. Cheung, J. L. Rempe, K. Y. Suh, and S. B. Kim. "CHF enhancement by vessel coating for external reactor vessel cooling." Nuclear Engineering and Design 236, no. 10 (May 2006): 1089–98. http://dx.doi.org/10.1016/j.nucengdes.2005.11.008.
Повний текст джерелаWei, Hui Ming, Xuan Zhang, and Tai Li Liu. "AP1000 Nuclear Reactor and Primary Loop Modeling Based on Relap5-3D and 3Keymaster Simulation Platform." Applied Mechanics and Materials 214 (November 2012): 510–14. http://dx.doi.org/10.4028/www.scientific.net/amm.214.510.
Повний текст джерелаVan Der Sluys, W. A., and R. H. Emanuelson. "Cyclic Crack Growth Behavior of Reactor Pressure Vessel Steels in Light Water Reactor Environments." Journal of Engineering Materials and Technology 108, no. 1 (January 1, 1986): 26–30. http://dx.doi.org/10.1115/1.3225836.
Повний текст джерелаPaulech, Juraj, Vladimír Kutiš, Gabriel Gálik, Jakub Jakubec, and Tibor Sedlár. "Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions." Strojnícky casopis – Journal of Mechanical Engineering 67, no. 1 (April 1, 2017): 87–92. http://dx.doi.org/10.1515/scjme-2017-0009.
Повний текст джерелаLiao, Jun, and Dan Utley. "Study on Reactor Vessel Air Cooling for Westinghouse Lead Fast Reactor." Nuclear Technology 206, no. 2 (April 29, 2019): 191–205. http://dx.doi.org/10.1080/00295450.2019.1599614.
Повний текст джерелаPopov, V., V. Mileikovskyi, and О. Tryhub. "Expert express assessment of the impact of heat and mass transfer processes on the residual life of the WWER-1000 reactor vessel due to cyclic damage." Ventilation, Illumination and Heat Gas Supply 39 (December 6, 2021): 6–28. http://dx.doi.org/10.32347/2409-2606.2021.39.6-28.
Повний текст джерелаSehgal, B. R., A. Karbojian, A. Giri, O. Kymäläinen, J. M. Bonnet, K. Ikkonen, R. Sairanen, et al. "Assessment of reactor vessel integrity (ARVI)." Nuclear Engineering and Design 235, no. 2-4 (February 2005): 213–32. http://dx.doi.org/10.1016/j.nucengdes.2004.08.055.
Повний текст джерелаSehgal, B. R., A. Theerthan, A. Giri, A. Karbojian, H. G. Willschütz, O. Kymäläinen, S. Vandroux, et al. "Assessment of reactor vessel integrity (ARVI)." Nuclear Engineering and Design 221, no. 1-3 (April 2003): 23–53. http://dx.doi.org/10.1016/s0029-5493(02)00343-6.
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