Evaluation of spent fuel pool temperature and water level during SBO (English)
- New search for: Mochizuki, Hiroyasu
- New search for: Mochizuki, Hiroyasu
In:
Annals of Nuclear Energy
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109
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548-556
;
2017
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Evaluation of spent fuel pool temperature and water level during SBO
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Contributors:Mochizuki, Hiroyasu ( author )
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Published in:Annals of Nuclear Energy ; 109 ; 548-556
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2017-06-02
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Size:9 pages
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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 109
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.
- 1
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A review of research progress in heat exchanger tube rupture accident of heavy liquid metal cooled reactorsWang, Gang et al. | 2017
- 9
-
RELAP5 uncertainty evaluation using ROSA/LSTF test data on PWR 17% cold leg intermediate-break LOCA with single-failure ECCSTakeda, Takeshi / Ohtsu, Iwao et al. | 2017
- 22
-
Uncertainty assessment for loss of flow accident of a 5MW pool-type research reactorYum, Soo-been / Park, Su-ki et al. | 2017
- 30
-
Onset of Nucleate Boiling for subcooled flow through a one-side heated narrow rectangular channelAl-Yahia, Omar S. / Jo, Daeseong et al. | 2017
- 41
-
Investigation of density wave instability in once-through superheated steam generators using SIGHTTang, Yang / Zhou, Zhiwei / Zhang, Dabin et al. | 2017
- 52
-
Numerical studies of a helical coil once-through steam generatorXia, Genglei / Yuan, Yuan / Peng, Minjun / Lv, Xing / Sun, Lin et al. | 2017
- 61
-
Conceptual design of thorium based epithermal spectrum reactorChoi, Hong Yeop / Park, Chang Je et al. | 2017
- 69
-
Characteristics and mechanism of bubble breakup in a bubble generator developed for a small TMSRSun, Licheng / Mo, Zhengyu / Zhao, Liang / Liu, Hongtao / Guo, Xie / Ju, Xiaofeng / Bao, Jingjing et al. | 2017
- 82
-
Study on operator’s SA reliability in digital NPPs. Part 3: A quantitative assessment methodLi, Peng-cheng / Zhang, Li / Dai, Li-cao / Li, Xiao-Fang et al. | 2016
- 92
-
Design of comprehensive diagnosis system in nuclear power plantLi, Wei / Peng, Min-jun / Yang, Ming / Xia, Geng-lei / Wang, Hang / Jiang, Nan / Ma, Zhan-guo et al. | 2017
- 103
-
Experimental analysis of steam mixing and thermal stratification phenomena related to small steel containment studiesWang, Shengfei / Wang, Yeyun / Zhuo, Weiqian / Niu, Fenglei / Yu, Yu / Guo, Zhangpeng / Shen, Yaou / Chen, Wei / Jiang, Xiaowei et al. | 2017
- 113
-
Supercritical transient analysis in coupled fuel debris systems of symmetric and asymmetric geometry using integral kinetic modelTuya, Delgersaikhan / Obara, Toru et al. | 2017
- 120
-
Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plantChen, Yen-Shu / Yuann, Yng-Ruey et al. | 2017
- 135
-
Numerical investigation of passive thermal-hydraulic performance of spent fuel dry-storage system for HTR-PMWang, Bing / Wang, Jinhua / Rizwan-uddin et al. | 2017
- 151
-
Performance verification of Passive Accident Mitigation Scheme (PAMS) under feedwater line break (FLB) accidentShi, Er-bing / Wang, Chang / Hao, Rui / Fang, Chengyue / Xia, Genglei et al. | 2017
- 162
-
Influence of reflector materials and core coolant on the characteristics of accelerator driven systemsPanza, F. / Osipenko, M. / Ricco, G. / Ripani, M. / Saracco, P. et al. | 2017
- 173
-
ATWS boron analysis for a BWR using the FNPK equationPolo-Labarrios, M.A. / Espinosa-Paredes, G. / Lopéz, R. / Nuñez-Carrera, A. / Huerta, A. / Vázquez-Rodríguez, R. et al. | 2017
- 180
-
Analysis of single phase flow instability in U-tubes of steam generatorYang, Bo / Wang, Chuan / Li, Xiao-Jun et al. | 2017
- 185
-
Study on operator's SA reliability in digital NPPs. Part 2: Data-driven causality model of SALi, Peng-cheng / Zhang, Li / Dai, Li-cao / Li, Xiao-fang et al. | 2017
- 192
-
Evaluation of dose rate variation during very long term storage of RBMK-1500 reactor used fuelŠmaižys, A. / Poškas, P. / Narkūnas, E. et al. | 2017
- 199
-
Assessment of spent nuclear fuel amounts to be managed based on disposal option in Republic of KoreaPark, Byung Heung et al. | 2017
- 208
-
An automatic marine-organism monitoring system for the intake water of the nuclear power plantTang, Zhihong / Cheng, Feng / Jin, Xiaoxiang / Sun, Li / Bao, RuoYu / Liu, Yang et al. | 2017
- 212
-
Modeling and experimental studies on air buoyant jets for application to small containmentsMa, Tengfei / Niu, Fenglei / Zhuo, Weiqian / Wang, Yeyun / Warraich, Taskeen / Azam, Safeer et al. | 2017
- 220
-
Investigation of radiation shielding of the Containment Filtered Venting System for the various operating conditionKim, Minhwa / Bang, Youngsuk / Lee, Doo Yong et al. | 2017
- 227
-
Finite volume lattice Boltzmann scheme for neutron/radiative transfer on unstructured meshWang, Yahui / Yan, Liming / Ma, Yu / Li, Wei et al. | 2017
- 237
-
Experimental investigation on transient heat transfer in 2×2 bundle during depressurization from supercritical pressureLi, Hongbo / Hu, Zhenxiao / Zhao, Meng / Gu, Hanyang / Lu, Donghua et al. | 2017
- 249
-
Detection model of accidental control rod drop in PWR reactors with in-core and ex-core nuclear instrumentation using Delaunay triangulationSouza, T.J. / Medeiros, J.A.C.C. / Gonçalves, A.C. et al. | 2017
- 260
-
Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSYHu, Tianliang / Cao, Liangzhi / Wu, Hongchun / Du, Xianan / He, Mingtao et al. | 2017
- 277
-
Neutronic calculations of the IAEA 10MW MTR benchmark reactor via finite element method using COMSOL multiphysics codeXoubi, Ned / Soliman, Abdelfattah Y. et al. | 2017
- 284
-
Use cases of Tucker decomposition method for reconstruction of neutron macroscopic cross-sectionsLuu, Thi Hieu / Guillo, Matthieu / Maday, Yvon / Guérin, Pierre et al. | 2017
- 298
-
Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactorLiu, Rong / Zhou, Wenzhong et al. | 2017
- 310
-
A study of photon interaction parameters in barium compoundsManjunatha, H.C. / Seenappa, L. / Chandrika, B.M. / Hanumantharayappa, Chikka et al. | 2017
- 318
-
Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5Feng, Tangtao / Zhang, Dalin / Song, Ping / Tian, Wenxi / Li, Wei / Su, G.H. / Qiu, Suizheng et al. | 2017
- 327
-
Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTFGuo, Juanjuan / Liu, Shichang / Shang, Xiaotong / Huang, Shanfang / Wang, Kan et al. | 2017
- 337
-
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1Lim, Kukhee / Cho, Yongjin / Whang, Seokwon / Park, Hyun Sun et al. | 2017
- 350
-
Effect of power uprate on core damage frequency in a MBLOCA with multiple operator actionsChen, Y.M. / Lee, M. / Chen, S.K. et al. | 2017
- 359
-
Polyvinyl alcohol-borate hydrogel containing magnetic adsorbent for surface decontaminationYang, Hee-Man / Hwang, Kyu Sun / Park, Chan Woo / Lee, Kune-Woo et al. | 2017
- 365
-
Effects of Gadolinium in Fe based amorphous ribbons with high boron contents on the neutron shielding efficiencyPark, Ji-Sung / Kim, Jungho / Yi, Seong-Hoon et al. | 2017
- 370
-
Validation of CFD analysis for rod bundle flow test with vaned spacer gridsChen, Xi / Du, Sijia / Zhang, Yu / Yu, Hongxing / Li, Songwei / Peng, Huanhuan / Wang, Wei / Zeng, Wei et al. | 2017
- 380
-
Calculation of resonance self-shielding factors in a round disk using the enlarged Doppler Broadening FunctionPalma, Daniel A.P. / Almeida, Guilherme G. / Gonçalves, Alessandro C. et al. | 2017
- 385
-
Rod ejection accident analysis for AP1000 with MOX/UOX mixed core loadingSelim, Hala K. / Amin, Esmat H. / Roushdy, Hassan E. et al. | 2017
- 396
-
A pulse-controlled modified-burst test instrument for accident-tolerant fuel claddingCinbiz, M. Nedim / Brown, Nicholas R. / Terrani, Kurt A. / Lowden, Rick R. / Erdman, Donald III et al. | 2017
- 405
-
Preliminary study of applying adjoint-based mesh optimization method to nuclear power plant safety analysisSon, Seongmin / Lee, Jeong Ik et al. | 2017
- 419
-
Experimental and numerical study on the circumferential pressure distribution on the wall of a 90° elbow pipe with circular sectionWang, Shiming / Ren, Cheng / Gui, Nan / Sun, Yanfei / Tu, Jiyuan / Yang, Xingtuan / Jiang, Shengyao et al. | 2017
- 431
-
Verification of kinetic capabilities of the GNOMER neutron diffusion codeMerljak, Vid / Kromar, Marjan / Trkov, Andrej et al. | 2017
- 440
-
Geometry pretreatment method for the 3D modular characteristic method based on AutoCADLiu, Zhouyu / Wu, Hongchun / Cao, Liangzhi et al. | 2017
- 451
-
Proposal to reload using MOX weapons grade in a BWR reactorHernandez, Hector / Castillo, Rogelio et al. | 2017
- 458
-
Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactorWang, Chenglong / Liu, Limin / Liu, Minghao / Zhang, Dalin / Tian, Wenxi / Qiu, Suizheng / Su, G.H. et al. | 2017
- 469
-
Fission yield covariance matrices for the main neutron-induced fissioning systems contained in the JEFF-3.1.1 libraryTerranova, N. / Serot, O. / Archier, P. / De Saint Jean, C. / Sumini, M. et al. | 2017
- 490
-
Design analysis of DC electromagnetic pump for liquid sodium–CO2 reaction experimental characterizationLee, Geun Hyeong / Kim, Hee Reyoung et al. | 2017
- 498
-
Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressureSong, Jung Hyun / Lee, Juhyung / Chang, Soon Heung / Jeong, Yong Hoon et al. | 2017
- 507
-
Diffusion theory model of the neutron number probability distribution in a subcritical multiplying assemblySaxby, J.E.M. / Prinja, Anil K. / Eaton, M.D. et al. | 2017
- 529
-
A CFD-based simulation of fluid flow and heat transfer in the Intermediate Heat Exchanger of sodium-cooled fast reactorZhang, Xiaolong / Tseng, Peichi / Saeed, Muhammad / Yu, Jiyang et al. | 2017
- 538
-
Design review and controllability assessment of the SMART-ITL secondary system for the SMART design with experimental investigationYun, Eunkoo / Bae, Hwang / Ryu, Sung-Uk / Yi, Sung-Jae / Park, Hyun-Sik et al. | 2017
- 548
-
Evaluation of spent fuel pool temperature and water level during SBOMochizuki, Hiroyasu et al. | 2017
- 557
-
Real-time simulations to enhance distributed on-line monitoring and fault detection in Pressurized Water ReactorsPeng, Min-jun / Wang, Hang / Yang, Xu / Liu, Yong-kuo / Guo, Liang-zhuang / Li, Wei / Jiang, Nan et al. | 2017
- 574
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Analytical solution of the Telegraph Point Reactor Kinetics model during the cold start-up of a nuclear reactorAltahhan, Muhammad Ramzy / Aboanber, Ahmed E. / Abou-Gabal, Hanaa H. et al. | 2017
- 583
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Accurate reflective boundary condition in the PN methodYousefi, Mostafa / Zolfaghari, A. / Minuchehr, A. / Abbassi, M.R. et al. | 2017
- 600
-
Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment typeLopez-Alonso, Emma / Papini, Davide / Jimenez, Gonzalo et al. | 2017
- 612
-
Capability of RELAP5 code to simulate the thermal-hydraulic characteristics of open natural circulationHou, Xiaofan / Sun, Zhongning / Lei, Wenjing et al. | 2017
- 626
-
A computational study of re-cycling the MTR research reactors with MOX fuel mixed with 241Am, 242Am and 243Am as burnable absorbers actinides using the MCNP4C codeShaaban, Ismail / Albarhoum, Mohamad et al. | 2017
- 635
-
Fluoride salt coolant properties for nuclear reactor applications: A reviewRomatoski, R.R. / Hu, L.W. et al. | 2017
- 648
-
Dynamic modeling of AP1000 steam generator for control system design and simulationWan, Jiashuang / Wu, Shifa / Nuerlan, Areai / Zhao, Fuyu et al. | 2017
- 658
-
Development and analysis of a regime map for predicting debris bed formation behaviorCheng, Songbai / Wang, Shixian / Jiang, Guangyu / Yu, Jiahuan / Qian, Yujia / Gong, Pengfeng / Cui, Jinjiang et al. | 2017
- 667
-
Neutronic modeling and calculations of the ETRR-2 MTR reactor using COMSOL multiphysics codeXoubi, Ned / Soliman, Abdelfattah Y. et al. | 2017
- 675
-
Sensitivity analysis for the weighting factor in the least-square method for the PWR on-line power-distribution monitoringLi, Zhuo / Cao, Liangzhi / Wu, Hongchun / Shen, Wei et al. | 2017
- 684
-
Track truncation method for improving the computational efficiency of 2D matrix MOCZheng, Yong / Peng, Minjun et al. | 2017
- 692
-
Energy Production Demonstrator and Material Testing Station optimization for Megawatt proton beamsPronskikh, Vitaly S. / Mokhov, Nikolai V. / Novitski, Igor / Tyutyunnikov, Sergey I. et al. | 2017
- 698
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A new cross section adjustment method of removing systematic errors in fast reactorsTakeda, Toshikazu / Yokoyama, Kenji / Sugino, Kazuteru et al. | 2017
- 705
-
Thermal hydraulics analysis of a helical coil steam generator of a small modular reactorZaman, Fakhar Uz / Qureshi, Kamran / Haq, Inamul / Siddique, Waseem et al. | 2017
- 712
-
Benchmark and demonstration of the CHD code for transient analysis of fast reactor systemsHellesen, C. / Qvist, S. et al. | 2017
- 720
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Multiplication factors of single pin hexagonal cells and VVER-1000 reactor assemblyPrabha, Hem / Karthikeyan, Ramamoorthy / Lajoie, Marc-A. / Marleau, Guy / Hébert, Alain et al. | 2017
- IFC
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Editorial board| 2017