External function for GOTHIC code to estimate critical heat flux conditions for in-vessel retention assessment (English)
- New search for: Pop, A.
- New search for: Petruzzi, A.
- New search for: Giannotti, W.
- New search for: Pop, A.
- New search for: Petruzzi, A.
- New search for: Giannotti, W.
In:
Nuclear Engineering and Design
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380
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2021
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ISSN:
- Article (Journal) / Electronic Resource
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Title:External function for GOTHIC code to estimate critical heat flux conditions for in-vessel retention assessment
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Contributors:
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Published in:
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Publisher:
- New search for: Elsevier B.V.
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Publication date:2021-05-21
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 380
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
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OECD nuclear energy agency CODAP database project on passive component operating experience. An international collaboration in materials researchLydell, Bengt / Forano, Diego Escrig / Riznic, Jovica et al. | 2021
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Lead/lead-alloy as a corrosion-resistant outer layer packaging material for high level nuclear waste disposalXiong, Yongliang / Wang, Yifeng / Roselle, Greg / Kim, Sungtae et al. | 2021
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Virtual round robin – A new opportunity to study NDT reliabilityVirkkunen, Iikka / Koskinen, Tuomas / Jessen-Juhler, Oskari et al. | 2021
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Hydraulic resistance of supercritical pressure water flowing in channels – A survey of literatureDeev, V.I. / Kharitonov, V.S. / Baisov, A.M. / Churkin, A.N. et al. | 2021
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Pressure buildup analysis of TRISO-coated fuel particlesBaghdasaryan, Nairi / Kozlowski, Tomasz et al. | 2021
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Time averaged tomographic measurements before and after dryout in a simplified BWR subchannel geometryRobers, Lukas / Adams, Robert / Bolesch, Christian / Prasser, Horst-Michael et al. | 2021
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An idea of employing a superconducting cylindrical linear induction pump for the nuclear power systemLi, Xiaodong / Liu, Chunyu / Wang, Xiaolie / Yang, Wenjiang / Macián-Juan, Rafael et al. | 2021
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Droplet entrainment by high-speed gas jet into a liquid poolSugimoto, Taro / Kaneko, Akiko / Abe, Yutaka / Uchibori, Akihiro / Kurihara, Akikazu / Takata, Takashi / Ohshima, Hiroyuki et al. | 2021
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Performance and size comparison of two-stage and three-stage axial turbines for a nitrogen gas Brayton cycle coupled with a sodium-cooled fast reactorChoi, Jae Hyun / Yoon, Jung / Eoh, Jaehyuk / Kim, Moo Hwan / Jo, HangJin et al. | 2021
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Influences of reprocessing separation efficiency on the fuel cycle performances for a Heavy Water moderated Molten Salt ReactorWu, Jianhui / Yu, Chenggang / Zou, Chunyan / Jia, Guobin / Cai, Xiangzhou / Chen, Jingen et al. | 2021
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Uncertainty and sensitivity analysis of the Phébus FPT3 testTiborcz, Livia / Hollands, Thorsten et al. | 2021
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Study on gas–liquid two-phase flow in the suction chamber of a centrifugal pump and its dimensionless characteristicsShao, Chunlei / Zhong, Gaochao / Zhou, Jianfeng et al. | 2021
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Experimental and numerical study of 19-pin disassembled fuel channel under severe accident conditionKumar, Rohit / Mishra, Manish / Gokhale, Onkar / Mukhopadhyay, D. et al. | 2021
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Thermal hydraulic modelling of grating effect for application to 3-dimensional analysis of hydrogen behavior in NPP containmentKim, Jongtae et al. | 2021
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Effect of inlet temperature on flow behavior and performance characteristics of supercritical carbon dioxide compressorBao, Wenrui / Yang, Ce / Wang, Wenli / Du, Yadong / Fu, Li et al. | 2021
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Response of electrical film thickness sensors to waves in the liquid filmPrasser, Horst-Michael et al. | 2021
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Failure identification in a nuclear passive safety system by Monte Carlo simulation with adaptive KrigingPuppo, L. / Pedroni, N. / Bersano, A. / Di Maio, F. / Bertani, C. / Zio, E. et al. | 2021
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BP neural network based reconstruction method for radiation field applicationsZhou, Wen / Sun, Guomin / Yang, Zihui / Wang, Hui / Fang, Li / Wang, Jianye et al. | 2021
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A numerical study of heat transfer enhancement by helically corrugated tubes in the intermediate heat exchanger of a very-high-temperature gas-cooled reactorHu, Qingxiang / Yuan, Kun / Peng, Wei / Zhao, Gang / Wang, Jie et al. | 2021
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Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlationYoshimura, Shusuke / Yamaguchi, Takuma / Ino, Keisuke / Furuya, Masahiro / Morooka, Shinichi et al. | 2021
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Reactor design of UPR-1: A MW-level reactor for unmanned underwater vehicle propulsion using low-enriched uraniumAzeem, Muhammad / Zheng, Youqi / Cao, Liangzhi et al. | 2021
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Editorial Board| 2021
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Review of modeling experience during operation and decommissioning of RBMK-1500 reactors. II. Radioactive waste managementRemeikis, V. / Grineviciute, J. / Duškesas, G. / Juodis, L. / Plukienė, R. / Plukis, A. et al. | 2021
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Comparative study with two reduced test facilities for air-cooled RCCS scaling lawKim, Chan Soo / Lisowski, Darius / Bae, Yoon Yeong / Kim, Jong Hwan / Lee, Sung Nam et al. | 2021
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Conversion factors bridging radiocative fission product distributions in the primary containment vessel of Fukushima daiichi npp and dose rates measured by the containment atmosphere monitoring systemUchida, Shunsuke / Pellegrini, Marco / Naitoh, Masanori et al. | 2021
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An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accidentUchida, Shunsuke / Karasawa, Hidetoshi / Kino, Chiaki / Pellegrini, Marco / Naitoh, Masanori / Ohsaka, Masahiko et al. | 2021
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Numerical modeling of radiation heat transfer from combusting droplets for a sodium fire analysisAoyagi, Mitsuhiro / Takata, Takashi / Uno, Masayoshi et al. | 2021
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Computational fluid dynamics assessment of the Helium-3 Enhanced Negative Reactivity Insertion (HENRI) system for the Transient REActor Test (TREAT) facilityBalderrama Prieto, Silvino A. / Mignot, Guillaume P.H. / Marcum, Wade R. et al. | 2021
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Investigating the possible advantage of using LM bonded gap instead of helium in Ap-1000 nuclear power reactorMohsen, Mohamed Y.M. / Abdel-Rahman, Mohamed A.E. / Hassan, Mohamed Safaa / Galahom, A. Abdelghafar et al. | 2021
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Fractal neutrons diffusion equation: Uniformization of heat and fuel burn-up in nuclear reactorEl-Nabulsi, Rami Ahmad et al. | 2021
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Evaluation of ASR in concrete using acoustic emission and deep learningAi, Li / Soltangharaei, Vafa / Ziehl, Paul et al. | 2021
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Review of modeling experience during operation and decommissioning of RBMK-1500 reactors. I. Safety improvement studies during operationRemeikis, V. / Grineviciute, J. / Duškesas, G. / Juodis, L. / Plukienė, R. / Plukis, A. et al. | 2020
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FIPD: The SFR metallic fuels irradiation & physics databaseYacout, Abdellatif M. / Mo, Kun / Oaks, Aaron / Miao, Yinbin / Sofu, Tanju / Mohamed, Walid et al. | 2021
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Improvement of the heat transfer enhancement model considering the droplet-wall heat transfer downstream of the flow blockage in the reflood phaseYoo, Jee Min / Yun, Byong Jo / Yoon, Han Young / Jeong, Jae Jun et al. | 2021
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CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000Khan, Irfan / Wang, Mingjun / Zhang, Yapei / Tian, Wenxi / Su, Guanghui / Qiu, Suizheng et al. | 2021
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External function for GOTHIC code to estimate critical heat flux conditions for in-vessel retention assessmentPop, A. / Petruzzi, A. / Giannotti, W. et al. | 2021