NuScale-like SMR Model Development and Applied Safety Analyses with the Code Chain Serpent-DYN3D-ATHLET (English)
- New search for: Diaz-Pescador, E.
- Further information on Diaz-Pescador, E.:
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https://orcid.org/0000-0001-5362-1925
- New search for: Bilodid, Y.
- New search for: Jobst, M.
- Further information on Jobst, M.:
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https://orcid.org/0000-0002-0151-3137
- New search for: Kliem, S.
- Further information on Kliem, S.:
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https://orcid.org/0000-0001-6654-6434
- New search for: Diaz-Pescador, E.
- Further information on Diaz-Pescador, E.:
-
https://orcid.org/0000-0001-5362-1925
- New search for: Bilodid, Y.
- New search for: Jobst, M.
- Further information on Jobst, M.:
-
https://orcid.org/0000-0002-0151-3137
- New search for: Kliem, S.
- Further information on Kliem, S.:
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https://orcid.org/0000-0001-6654-6434
In:
Nuclear Engineering and Design
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418
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2024
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ISSN:
- Article (Journal) / Electronic Resource
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Title:NuScale-like SMR Model Development and Applied Safety Analyses with the Code Chain Serpent-DYN3D-ATHLET
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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:2024-01-06
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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:NuScale-SMR , iPWR , Boron dilution , Steam line break , Serpent-DYN3D-ATHLET , BOC , Beginning Of Cycle , CVCS , Chemical Volume Control System , DHRS , Decay Heat Removal System , EOC , End Of Cycle , ESFAS , Engineered Safety Features Actuation System , FSAR , Final Safety Analysis Report , FWIV , Feedwater Isolation Valve , HCO , Heat Conduction Object , HCSG , Helical Coil Steam Generator , LHGR , Linear Heat Generation Rate , MPS , Module Protection System , MDNBR , Minimum Departure from Nucleate Boiling Ratio , MSIV , Main Steam Isolation Valve , ODE , Ordinary Differential Equation , PWR , Pressurized Water Reactor , RCS , Reactor Coolant System , RPV , Reactor Pressure Vessel , SDM , Shutdown Margin , SG , Steam Generator , SMR , Small Modular Reactor
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Source:
Table of contents – Volume 418
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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Implementation of the design extension conditions concept in the Czech Republic regulatory framework and NPPsKrál, Pavel / Krhounková, Jelena et al. | 2023
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Thermal-Mechanical performance analysis of a petal-shaped fuel rod under RIA conditionHe, Binxian / Hou, Yandong / Zhang, Wenchao / Meng, Xiangfei / Cai, Weihua et al. | 2023
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Comparison of accelerated and non-accelerated post-LOCA simulationŠaršounová, Zuzana / Žák, Pavel / Dragoun, Dominik et al. | 2024
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Effectiveness re-evaluation on the intentional primary system depressurization during Zion-like Westinghouse PWR station blackout considering pressure dependence of radionuclides releaseAddad, Yacine / Hidaka, Akihide / Alhammadi, Abdulla Ahmed / Al Kaabi, Ahmed / Al Ameri, Saeed et al. | 2023
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Numerical heat transfer to LBE flow in a wire-wrapped 19-rod bundle using an OpenFOAM-based solver: fourParameterFoamWu, Jie / Su, Xingkang / Gong, Ziqi / Cai, Jiejin / Gu, Long et al. | 2024
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From debris bed formation to self-leveling behaviors in core disruptive accident of sodium-cooled fast reactorXu, Ruicong / Cheng, Songbai et al. | 2024
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Assessing the collaborative quality value in nuclear power intelligent construction: A value chain analysis method based on double-layer GERT networkXu, Mengyu / Yi, Shuping / Si, Hengyuan / Gao, Xinyu / Liu, Chun / Xiong, Shiquan / Feng, Yixiong / Yi, Qian et al. | 2024
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Plasticity-based evaluation method for in-plane shear strength of steel-plate composite elementGuo, Shuheng / Gong, Jinxin / Cui, Yao / Sun, Yunlun / Wang, Xingchao et al. | 2024
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ANItA – A new Swedish national competence centre in new nuclear power technologyHåkansson, Ane et al. | 2023
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A numerical investigation of thermal stress induced cracking pattern in the solidifying nuclear fuel droplet during MFCIChandra Kumar, M. / Jasmin Sudha, A. / Venkatraman, B. et al. | 2023
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Scaling analysis for the condensation induced water hammer effect in horizontal pipeYang, Yili / Zhao, Jiaming / Zhao, Danfeng / Li, Xinrui / Guo, Wentao / Wang, Shengfei et al. | 2023
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NuScale-like SMR Model Development and Applied Safety Analyses with the Code Chain Serpent-DYN3D-ATHLETDiaz-Pescador, E. / Bilodid, Y. / Jobst, M. / Kliem, S. et al. | 2024
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The role of thermodynamic effects in Cavitation: Impacts on cavitation structure and propagation of cavitation noiseXu, Bo / Hu, Hongfei / Yang, Kuang / Wang, Haijun et al. | 2024
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SubChanFlow and VIPRE codes benchmark for VVER-1000Syblik, Jan / Musa, Alis Ruscak / Malacka, Milan / Mazzini, Guido et al. | 2024
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Preface for Special Issue “NFT-09: LT&EE&LV”Kaliatka, Algirdas et al. | 2024
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Investigation of prototypical corium interaction with samples of VVER-1000 in-vessel and ex-vessel structuresHrbek, Jan / Paukov, Mykhaylo / Mészáros, Bence / Sears, Anna / Vokáč, Petr / Janda, Tomáš / Kotouč, Miroslav et al. | 2023
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A proposed refueling scheme for the modular pebble bed reactorElhefnawy, A.H. / Abou Gabal, Hanaa / Gaheen, M.A. / El Saghir, Ahmed et al. | 2023
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The Feasibility of Small Modular Reactors (SMRs) in the Energy Mix of Saudi ArabiaAl-Salhabi, Abdalaziz / Alhabib, Ahmad / Alharbi, Talal / Aljohani, Mohammed / Shams, Afaque / Al-Athel, Khaled / Alwafi, Anas et al. | 2023
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The impact of fast spectrum graphite moderated systems on thermal spectrum graphite moderated reactors through the resonance physics of n+12CLentchner, Gabriel / Worrell, Kathryn / Satvat, Nader / Pevey, John / Marshall, William / Sobes, Vladimir et al. | 2024
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Editorial Board| 2024
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A computational framework for probabilistic structural assessments of reactor components requiring complex code workflowsEl Bouzidi, S. / Forgues, F. / Ortega Pelayo, R.E. / Chen, Q. / John, A. / Trottier, A. / Pfeiffer, S. et al. | 2023
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The operator and the seven small modular reactors — An estimate of the number of reactors that a single reactor operator can safely operateHartmann, Jens / Hyvärinen, Juhani / Rintala, Ville et al. | 2024
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Numerical analysis and validation on heat transfer characteristics and correlation of molten salt in pebble bed channelWang, S.W. / Zhou, C. / Wang, N.X. / Cai, C.X. / Zhu, H.H. / Zou, Y. et al. | 2024
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Applications of the FEM to pipe whip analysis using coupled modelling techniquePate, Sushant Bhalchandra / Solomon, Isaac Samuel Michael / Dundulis, Gintautas / Griskevicius, Paulius et al. | 2024
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Validation of the dynamic simulation capabilities of Serpent2/Subchanflow using experimental data from the research reactor SPERT IV D-12/25Carlos Almachi, Juan / Sánchez-Espinoza, Victor / Imke, Uwe / Stieglitz, Robert / Margulis, Marat et al. | 2023
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Full scope scaling analysis and recommendations for PWR SGTR scenariosMartin, Kevin / Martinez-Quiroga, V. / Freixa, Jordi et al. | 2023
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Design and development of a neutron detection based novel criticality accident alarm system (CAAS) using liquid activation techniqueSathian, Deepa / Kannan, Umasankari / Kulkarni, D.B. / Deo, Kapil / Bakshi, A.K. / Sapra, B.K. et al. | 2023
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JENDL-5.0 nuclear data sensitivity, uncertainty, and similarity analyses on the criticality of RSG GAS multipurpose research reactorLiem, Peng Hong / Hartanto, Donny et al. | 2024
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Predicting Critical Heat Flux in Rectangular Channels: Which Correlation to Trust?Bertocchi, F. / de Kock, I.J.V. / Vega, C.A. et al. | 2024
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Effects of circumferential weld-induced imperfections on the buckling behavior of fabricated steel toroidal shellsTangbanjongkij, Chanachai / Chucheepsakul, Somchai / Pulngern, Tawich / Jiammeepreecha, Weeraphan et al. | 2024
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African Nuclear Educational Network (AFRA-NEST): Assessment, challenges, and the way forwardHassan, Mohamed H. et al. | 2023
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Contribution of IAEA coordinated research projects to light water reactors advanced technology fuel testing and simulationZhang, Jinzhao / Xu, Peng / Sevecek, Martin / Sim, Ki Seob / Khaperskaia, Anzhelika et al. | 2024
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Study on sandstorm hazard evaluation for inland nuclear power plant siteDing, Shuxian / Wang, Shaohui / Feng, Wanxin / Yu, Yu et al. | 2024
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Three-phase VOF modeling of water jet – molten metal interactionYakush, S.E. / Sivakov, N.S. / Melikhov, O.I. / Melikhov, V.I. et al. | 2023
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Heat transfer optimization of uo2-mo fuel using genetic algorithmsGorton, Jacob P. / McDuffee, Joel L. / Snarr, Patrick L. / Petrie, Christian M. / Nelson, Andrew T. et al. | 2023
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Study on the liquid level characteristics and reconstruction strategy of the in-vessel pressurizer under ocean conditionsLi, Dongyang / Quan, Zixuan / Zhang, Biao / Cui, Hefeng / Wei, Tianyi / Tan, Sichao / Tian, Ruifeng et al. | 2023
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The integration of seawater desalination system with nuclear power plant: Operational flexibility enhancement and thermo-economic performancesWu, Qingyang / Li, Gen / Yin, Junjie / Liu, Ming / Yan, Junjie / Deguchi, Yoshihiro et al. | 2023
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Core design: Review & perspectives in SpainMiró, R. / Barrachina, T. / Soler, A. / Riverola, J. / Guerrero, J.A. / Concejal, A. / Ortego, A. / Modrego, J.L. / Rodríguez, S. / Cabellos, O. et al. | 2023
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Exploring the effects of Al and Si dopants on the accident tolerant fuels of UO2 pellets for light water reactorNgarayana, I Wayan / Langenati, Ratih / Rohanda, Anis / Subhan, Muhammad / Khakim, Azizul / Kusuma, M. Hadi / Suryaman, Ganisa K. / Rahmadi, Gagad / Buana, Odi / Ilham Bayquni, Muhammad et al. | 2024
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Investigation on thermohydraulic characteristics of novel superheated steam supply system for low temperature nuclear heating reactorLi, Zongyang / Hao, Wentao / Zhang, Wenwen / Li, Weihua / Yang, Xingtuan et al. | 2024
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Highly detailed structural integrity assessment of the reactor pressure vessel nozzle of Atucha-I during a pressurized thermal shock eventRabazzi, Santiago M. / Albanesi, Alejandro E. / Nervi, Juan E. Ramos / Signorelli, Javier W. et al. | 2024
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Refractory geopolymers: Thermal shock resistant material for nuclear safetyMészáros, Bence / Hrbek, Jan / Paukov, Mykhaylo / Černý, Zbyněk / Rozsypal, Pavlína / Komrska, Jan / Tyrpekl, Václav et al. | 2024
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Solidification of radioactive spent liquid scintillator wastes: Effect of additives on the compressive strength of the solidified formsChen, Lei / Li, Junfeng / Wang, Jianlong et al. | 2024
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Fuel depletion study of the molten salt demonstration reactorCreasman, Sarah Elizabeth / Jay Harrison, T. / Heilbronn, Lawrence H. et al. | 2023
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Spanish contribution to the development and application of probabilistic safety analysis: Experience and future challengesMartorell, S. / Martón, I. / Sánchez, A. / Courtin, S. / Queral, C. / Meléndez, E. / Olivar, F. / García-Zamorano, A. / Marín, R. / Díaz, P. et al. | 2023
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Core design optimization of a 200 MWt pressurized water SMR using evolutionary simulated annealingHoang, Van-Khanh / Phan, Giang T.T. / Tran, Viet-Phu / Chu, Thoi-Nam / Nguyen, Huu-Tiep / Phan, Haidang / Bui, Van-Loat / Tran, Hoai-Nam et al. | 2023
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Model predictive control of a Lab-Scale thermal energy storage system in RELAP5-3DWallace, Jaron / Hill, Daniel / Thurston, David / Hedengren, John / Memmott, Matthew et al. | 2024
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A numerical model to investigate the irradiation effect on the dynamics of nuclear fuel bundlesElbanhawy, Osama / Hassan, Marwan / Mohany, Atef / Kishawy, Hossam et al. | 2023
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Impact of LWR assembly structural features on cladding burst behavior under LOCA conditionsSchappel, Danny / Capps, Nathan et al. | 2023
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Feasibility study of desalination plant powered by SMRBuzzetti, Renato / Lo Frano, Rosa / Cancemi, Angelo Salvatore et al. | 2023
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Sensitivity analysis of simulated premixed layer and vapour explosion in stratified configurationKokalj, Janez / Uršič, Mitja / Leskovar, Matjaž / Meignen, Renaud et al. | 2024
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Fuel integrity evaluation for the shutdown BWR-4 plant during LOCA eventHsu, Keng-Hsien / Dai, Liang-Che / Chen, Yen-Shu / Yuann, Yng-Ruey et al. | 2024
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Myrmecia: Failure analysis and thermodynamic coupled simulation program for heat pipe in micro reactor based on MOOSEwei, Kun / Zhang, Shuaishuai / Zheng, Jianxiang / Yu, PeiZhao / Miao, Huifang et al. | 2024
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Improved cellular automata modeling of corrosion/oxidation mechanism of stainless steel in LBEChen, Junyao / Lyu, Xuefeng / Yu, Yu / Liu, Bin / Liu, Fang / Li, Xichen / Zhang, Heng / Guo, Zhangpeng et al. | 2023
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N-Euler mathematical modelling and numerical simulation of liquid–gas–solid flowsBaraglia, F. / Laviéville, J. / Mérigoux, N. / Simonin, O. et al. | 2023
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Estimation of uncertainty in computation of importance factors and probability of undesirable events for safety-critical multi-unit systems, based on Binary Decisions DiagramsUlmeanu, Anatoli Paul / Nistor-Vlad, Roxana-Mihaela / Dumitrescu, Ana-Victoria / Tanasiev, Vladimir et al. | 2023
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Review of spacer grid to rod fretting in pressurized water reactorRicciardi, Guillaume / Faucher, Vincent / Rossi, Lionel / François, Fabrice / Collard, Bruno / Bardet, Philippe et al. | 2024
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Development of a fission gas release and swelling model for sodium-cooled fast reactor fuelsGuo, Jingyu / Tan, Shaojie / Wang, Kai / Cheng, Songbai / Zhou, Wenzhong et al. | 2024
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Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycleAmatullah, Amila / Permana, Sidik / Irwanto, Dwi / Aimon, Akfiny Hasdi et al. | 2024