Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods (English)
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In:
Nuclear Engineering and Design
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410
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2023
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods
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Contributors:
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Publisher:
- New search for: The Author(s)
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Publication date:2023-05-17
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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 410
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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Sensitivity of UO fuel performance to microstructural evolutions driven by dilute additivesCheniour, Amani / Sweet, Ryan T. / Nelson, Andrew T. / Wilson, Brandon A. / Shields, Ashley E. et al. | 2023
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Some recent progress in reactor core thermal-hydraulics modellingCheng, Xu / Liu, Xiaojing et al. | 2023
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Development of a statistical evaluation method for core hot spot temperature in sodium-cooled fast reactor under natural circulation conditionsDoda, Norihiro / Igawa, Kenichi / Iwasaki, Takashi / Murakami, Satoshi / Tanaka, Masaaki et al. | 2023
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Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methodsRochman, D. / Taforeau, J. / Simeonov, T. / Shama, A. et al. | 2023
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Modelling of a passive hydraulic lock concept for the mitigation transfer tubes in a SFR coreBelliard, Michel / Bajard, Sophie / Cadiou, Thierry et al. | 2023
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A novel experimental observation of the gravity-driven flashing of metastable water in a heated poolMartin, Jimmy / Ruyer, Pierre / Duponcheel, Matthieu / Bartosiewicz, Yann et al. | 2023
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The modeling of interaction between fuel element cladding and steamParfenova, Elena S. / Knyazeva, Anna G. et al. | 2023
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Proper orthogonal decomposition energy analysis in a nuclear reactor coolant pump based on PIV at the best efficiency pointNi, Dan / Huang, Shiyuan / Zhang, Yang / Gao, Bo / Lu, Sheng et al. | 2023
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Fast reactor multi-scale and multi-physics modelling at NRGZwijsen, Kevin / Uitslag-Doolaard, Heleen / Roelofs, Ferry / Cervi, Eric / Stempniewicz, Marek et al. | 2023
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Steady-state and power transient critical heat flux experiments of FeCrAl and Zircaloy claddings under saturated pool boilingHe, Mingfu / Chen, Minghui et al. | 2023
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OECD/NEA R&D priorities for loss-of-cooling and loss-of-coolant accidents in Spent-Fuel-PoolsMartin, J. / Trégourès, N. et al. | 2023
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Experimental study on kinetic oxidation of graphite IG-110 by steamWang, Chengqi / Sun, Xiaodong et al. | 2023
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Editorial Board| 2023
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Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactorGuo, Yanlei / Yang, Congxin / Wang, Yan / Lv, Tianzhi et al. | 2023
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Transient characteristics analysis of residual heat removal system for Helium-Xenon mixture cooled small reactor systemWang, Xianbo / Dong, Xianmin / Li, Zhongchun / Wang, Xiaoyu / Zhao, Fulong / Tan, Sichao et al. | 2023
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A review on the external cooling of the pressure vessel lower head in nuclear power plantHou, Yandong / Cai, Rui / Huang, Xianyao / Zhang, Chao / Li, Weichao / Cai, Benan / Gao, Chuntian / Xiang, Yan et al. | 2023
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ESMOC 2021 – 3rd Energy System Modeling and Optimization Conference, December 5–7, 2022, NIT Durgapur, IndiaParuya, Swapan / D'Auria, Francesco et al. | 2023
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A greedy algorithm for wavelet-based time domain response spectrum matchingNie, Jinsuo / Graizer, Vladimir / Seber, Dogan et al. | 2023
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CFD investigation of flow and heat transfer of supercritical CO2 in wire wrapped rod bundleLiu, Sichao / Zhu, Dahuan / Li, Xiaochang / Tian, Ruifeng et al. | 2023
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TRISO fuel performance analysis: Uncertainty quantification toward optimizationBaghdasaryan, Nairi / Jiang, Wen / Hales, Jason / Kozlowski, Tomasz / Krajewska, Zuzanna et al. | 2023
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State-of-the-art and review of condensation heat transfer for small modular reactor passive safety: Computational studiesBhowmik, Palash K. / Ormiston, Scott J. / Schlegel, Joshua P. / Chowdhury, Debasish et al. | 2023
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Experimental and modelling results of the QUENCH-20 experiment with BWR test bundleStuckert, Juri / Bechta, Sevostian / Hollands, Thorsten / Isaksson, Patrick / Steinbrueck, Martin et al. | 2023
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Miniature DC electromagnetic pumps of molten lead and sodium to support development of Gen-IV nuclear reactorsAltamimi, Ragai / El-Genk, Mohamed S. et al. | 2023
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Characterization of local parameters of inclined upward air–water bubbly two-phase flows in a round pipeRyan, Drew / Kim, Seungjin et al. | 2023
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Subchannel thermal hydraulic analysis of 5 × 5 rod bundle with CRUD layerDeng, Rining / Kai, Mingdong / Cai, Jiejin et al. | 2023
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Seismic resilience assessment of Small Modular Reactors by a Three-loop Monte Carlo SimulationDi Maio, Francesco / Bani, Lorenzo / Zio, Enrico et al. | 2023
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Design of a Direct numerical Simulation of flow and heat transfer in a T-junctionAjay Kumar, Aniketh / Mathur, Akshat / Gerritsma, Marc / Komen, Ed et al. | 2023
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Influence of non-uniform inflow on performance of reactor coolant pump and improved designLiu, Lei / Yin, Junlian / Chen, Yunzhang / Feng, Lei / Liu, Lijun et al. | 2023