Strength assessment of SMART design against anticipated transient without scram (English)
- New search for: Chung, Young-Jong
- New search for: Kim, Hyung-Rae
- New search for: Chun, Ji-Han
- New search for: Kim, Soo-Hyung
- New search for: Bae, Kyoo-Hwan
- New search for: Chung, Young-Jong
- New search for: Kim, Hyung-Rae
- New search for: Chun, Ji-Han
- New search for: Kim, Soo-Hyung
- New search for: Bae, Kyoo-Hwan
In:
Progress in nuclear energy
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85
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617-623
;
2015
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ISSN:
- Article (Journal) / Print
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Title:Strength assessment of SMART design against anticipated transient without scram
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Contributors:Chung, Young-Jong ( author ) / Kim, Hyung-Rae ( author ) / Chun, Ji-Han ( author ) / Kim, Soo-Hyung ( author ) / Bae, Kyoo-Hwan ( author )
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Published in:Progress in nuclear energy ; 85 ; 617-623
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Publisher:
- New search for: Elsevier Science B.V., Amsterdam.
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Publication date:2015-01-01
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Size:7 pages
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ISSN:
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Type of media:Article (Journal)
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Type of material:Print
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Language:English
- New search for: 333.7924
- Further information on Dewey Decimal Classification
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Classification:
DDC: 333.7924 -
Source:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents – Volume 85
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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Hydrodynamic and mass transfer studies of 125 mm centrifugal extractor with 30% TBP/nitric acid systemMandal, Kinkar / Kumar, Shekhar / Vijayakumar, V. / Mudali, U. Kamachi / Ravisankar, A. / Natarajan, R. et al. | 2015
- 11
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Breed-and-burn strategy in a fast reactor with optimized starter fuelHuang, Jinfeng / Han, Jianlong / Cai, Xiangzhou / Ma, Yuwen / Li, Xiaoxiao / Zou, Chunyan / Yu, Chenggang / Chen, Jingen et al. | 2015
- 17
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Estimation of relative power distribution and power peaking factor in a VVER-1000 reactor core using artificial neural networksPirouzmand, Ahmad / Kazem Dehdashti, Morteza et al. | 2015
- 28
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Control simulation and study of load rejection transient for AP1000Wang, Pengfei / Chen, Zhi / Zhang, Rui / Sun, Jian / He, Zhengxi / Zhao, Fuyu / Wei, Xinyu et al. | 2015
- 44
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System assessment of an FPGA-based RPS for ABWR nuclear power plantLu, Jun-Jen / Hsu, Teng-Chieh / Chou, Hwai-Pwu et al. | 2015
- 56
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SLIMM-Scalable LIquid Metal cooled small Modular Reactor: Preliminary design and performance analysesEl-Genk, Mohamed S. / Palomino, Luis M. et al. | 2015
- 71
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TRACY and SILENE Benchmark Phase II evaluation by TRACE codeLiem, Peng Hong / Naito, Yoshitaka et al. | 2015
- 83
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Evaluation of contribution of thermal radiation in transferring decay heat to the moderator, in case of 18 rod bundle facility, simulating advanced nuclear reactorsBopche, Santosh B. / Sridharan, Arunkumar / Nayak, Arun K. et al. | 2015
- 96
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Experimental investigation of natural circulation instability in a BWR-type small modular reactorShi, Shanbin / Schlegel, Joshua P. / Brooks, Caleb S. / Lin, Yu-Chen / Eoh, Jaehyuk / Liu, Zhuo / Zhu, Qingzi / Liu, Yang / Hibiki, Takashi / Ishii, Mamoru et al. | 2015
- 108
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Two group, three dimensional diffusion theory coupled with single heated channel model: A study based on xenon transient simulation of Tehran research reactorHosseini, Mohammad / Khalafi, Hossein / Khakshournia, Samad et al. | 2015
- 121
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A numerical assessment of copper oxide and alumina nanoparticles during CHF occurrenceRabiee, Ataollah / Atf, Alireza et al. | 2015
- 130
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Numerical simulation on single bubble behavior during Al2O3/H2O nanofluids flow boiling using Moving Particle Simi-implicit methodWang, Yun / Wu, Jun Mei et al. | 2015
- 140
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Large eddy simulation of rough and smooth liquid plunging jet processesKhezzar, Lyes / Kharoua, Nabil / Kiger, Kenneth T. et al. | 2015
- 156
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The design and utilization of a high-temperature helium loop and other facilities for the study of advanced gas-cooled reactors in the Czech RepublicBerka, Jan / Hlinčík, Tomáš / Víden, Ivan / Hudský, Tomáš / Vít, Jan et al. | 2015
- 164
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Slug flow in a vertical narrow rectangular channel – Laminar and turbulent regimes in the main flow and turbulent regime in the wake region of the Taylor bubbleWang, Yang / Yan, Changqi / Xing, Dianchuan / Jin, Guangyuan / Sun, Licheng / Yang, Guang et al. | 2015
- 178
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Thermodynamic analysis of a solid nuclear fuel element surrounded by flow of coolant through a concentric annular channelPoddar, Antarip / Chatterjee, Rajeswar / Chakravarty, Aranyak / Ghosh, Koushik / Mukhopadhyay, Achintya / Sen, Swarnendu et al. | 2015
- 192
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BDD algorithms based on modularization for fault tree analysisDeng, Yunli / Wang, He / Guo, Biao et al. | 2015
- 200
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Solution of PHWR 3D kinetics benchmark using TRIKIN codeKumar, Rakesh / K, Obaidurrahman / Doshi, J.B. / Gaikwad, Avinash J. et al. | 2015
- 213
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Searching for enrichment and gadolinia distributions in BWR fuel lattices through a Heuristic-Knowledge MethodMontes-Tadeo, José-Luis / Perusquía-del-Cueto, Raúl / Martín-del-Campo, Cecilia / Castillo, Alejandro / François, Juan-Luis / Ortiz-Servin, Juan-José et al. | 2015
- 228
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Development of DETAC and its application to the hydrogen detonation analysisHuang, Tao / Tian, W.X. / Zhang, Y.P. / Su, G.H. / Qiu, S.Z. / Yang, Xingtuan / Yin, Huaqiang et al. | 2015
- 239
-
Rheological characterization of buffered boric acid aqueous solutions in light water reactorsHassan, Yassin A. / Osturk, Serdar / Lee, Saya et al. | 2015
- 254
-
Improvement of a calculation procedure of neutron-flux distribution for radioactivity inventory estimation for decommissioning of nuclear power plantsTanaka, Ken-ichi / Ueno, Jun / Adachi, Masataka / Chiba, Satoshi et al. | 2015
- 271
-
Molecular dynamics calculations of heat conduction in actinide oxides under thermal gradientMatsumoto, Taku / Arima, Tatsumi / Inagaki, Yaohiro / Idemitsu, Kazuya / Kato, Masato / Uchida, Teppei et al. | 2015
- 277
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Radionuclide transport in shallow groundwaterTestoni, Raffaella / Levizzari, Riccardo / De Salve, Mario et al. | 2015
- 291
-
Self-induced electrostatic-boosted radioisotope heat sourcesArias, Francisco J. / Parks, Geoffrey T. et al. | 2015
- 297
-
The use of ionising radiation to image nuclear fuel: A reviewParker, Helen M. O'D. / Joyce, Malcolm J. et al. | 2015
- 319
-
Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management GuidelineLi, Y.B. / Cao, X.W. et al. | 2015
- 325
-
Thermal and stress analysis of window target for accelerator-driven sub-critical system during beam trip transientsJin, Ming / Chai, Youqi / Xue, Sha / Wang, Gang / Chen, Zhibin et al. | 2015
- 333
-
Plutonium fingerprinting in nuclear forensics of spent nuclear fuelLantzos, I. / Kouvalaki, Ch / Nicolaou, G. et al. | 2015
- 337
-
Preliminary simulation of fuel dispersion in a Lead-Bismuth Eutectic (LBE)-cooled research reactorWang, Zhen / Wang, Gang / Gu, Zhixing / Jin, Ming / Zhao, Zhumin et al. | 2015
- 344
-
The use of heat balance method in the thermal power calibration of Nigeria Research Reactor-1 (NIRR-1)Agbo, S.A. / Ahmed, Y.A. / Yahaya, B. / Iliyasu, U. et al. | 2015
- 352
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Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000Mao, Keyou / Wang, Jun / Li, Longze / Zhang, Yapei / Tian, Wenxi / Su, Guanghui / Qiu, Suizheng / Corradini, Michael L. et al. | 2015
- 366
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Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD codeGe, Jian / Zhang, Dalin / Tian, Wenxi / Wang, Kunpeng / Qiu, Suizheng / Su, G.H. et al. | 2015
- 375
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Technetium transmutation in thin layer coating on PWR fuel rodsLiu, Bin / Huang, Liming / Tu, Jing / Liu, Fang / Cao, Qiong / Jia, Rendong / Li, Xiang / Cai, Jin et al. | 2015
- 384
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Safety analysis of reactivity insertion accidents in a heavy water nuclear research reactor core using coupled 3D neutron kinetics thermal-hydraulic system code techniqueTitouche Kouidri, W. / Letaim, F. / Boucenna, A. / Boulhaouchet, M.H. et al. | 2015
- 391
-
Investigation of gamma radiation shielding properties of various oresOto, Berna / Yıldız, Nergiz / Akdemir, Fatma / Kavaz, Esra et al. | 2015
- 404
-
Gas-cooled reactor thermal hydraulic analyses with MELCORBeeny, Bradley / Vierow, Karen et al. | 2015
- 415
-
Vertical upward two-phase flow CFD using interfacial area transport equationChuang, Tien-Juei / Hibiki, Takashi et al. | 2015
- 428
-
Development of the ALFRED reactor full power mode control systemPonciroli, Roberto / Cammi, Antonio / Della Bona, Alessandro / Lorenzi, Stefano / Luzzi, Lelio et al. | 2015
- 441
-
A thermal model to characterize the flattening effect of a nuclear fuel element in an annular channel using simple analytical approachPoddar, Antarip / Chatterjee, Rukmava / Chakravarty, Aranyak / Ghosh, Koushik / Sen, Swarnendu / Mukhopadhyay, Achintya et al. | 2015
- 454
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Application of CNUREAS and MCNP5 codes to VVER-1000 MOX Core Computational BenchmarkŞentürk Lüle, Senem / Özdemir, Levent / Erdoğan, Adem et al. | 2015
- 462
-
CFD study of an air–water flow inside helically coiled pipesColombo, Marco / Cammi, Antonio / Guédon, Gaël Raymond / Inzoli, Fabio / Ricotti, Marco Enrico et al. | 2015
- 473
-
Galerkin and Generalized Least Squares finite element: A comparative study for multi-group diffusion solversHosseini, Seyed Abolfazl / Saadatian-Derakhshandeh, Farahnaz et al. | 2015
- 491
-
Does it really make sense to use fission gas plenums in a lead-bismuth-cooled fast reactor?Arias, Francisco J. / Parks, Geoffrey T. et al. | 2015
- 498
-
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part I: Uranium fuel cycleLindley, Benjamin A. / Fiorina, Carlo / Gregg, Robert / Franceschini, Fausto / Parks, Geoffrey T. et al. | 2015
- 511
-
Effect of high density dispersion fuels on transient behavior of MTR type research reactor under multiple reactivity transientsNasir, Rubina / Butt, Muhammad Kamran / Mirza, Sikander M. / Mirza, Nasir M. et al. | 2015
- 518
-
Prediction of MgO volume fraction in an ADS fresh fuel for the scenario code CLASSThiollière, N. / Courtin, F. / Leniau, B. / Mouginot, B. / Doligez, X. / Bidaud, A. et al. | 2015
- 525
-
Spent fuel interrogation using delayed fast neutron spectrum at Missouri University of Science and Technology ReactorAkyurek, T. / Usman, S. et al. | 2015
- 541
-
Numerical investigation of the CANDU moderator thermal-hydraulics using the CUPID codeChoi, Su Ryong / Jeong, Jae Jun / Lee, Jae Ryong / Yoon, Han Young / Kim, Hyoung Tae et al. | 2015
- 548
-
Method of characteristics – A review with applications to science and nuclear engineering computationEklund, Matthew / Alamaniotis, Miltiadis / Hernandez, Hermilo / Jevremovic, Tatjana et al. | 2015
- 568
-
Independent fission yields studied based on Langevin equationAritomo, Yoshihiro / Chiba, Satoshi / Nishio, Katsuhisa et al. | 2015
- 573
-
The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal systemXi, Mengmeng / Wu, Yingwei / Tian, Wenxi / Su, G.H. / Qiu, Suizheng et al. | 2015
- 588
-
Comparative study for modeling reactor internal geometry in CFD simulation of PWR and PHWR internal flow – Nuclear regulatory perspectiveLee, Gong Hee / Bang, Young Seok / Cheong, Ae Ju et al. | 2015
- 600
-
Synthesis and characterization of ultra-fine well-dispersed thoria nano spheres through reduction reactions in nitrate bathYousefi, Taher / Torab-Mostaedi, Meisam / Sohbatzadeh, Hojbar / Keshtkar, Ali Reza / Aghayan, Hassan / Maragheh, Mohammad Ghannadi et al. | 2015
- 605
-
Three-dimensional analysis of flow blockage accident in Tehran MTR research reactor core using CFDDavari, Amin / Mirvakili, Seyed Mohammad / Abedi, Ebrahim et al. | 2015
- 613
-
Heavy Water Zero Power Reactor (HWZPR) mixed core first criticality, calculation and experimentsKhorsandi, J. / Nasr, Z. / Salimi, R. / Adavoodi, M. / Khalafi, H. et al. | 2015
- 617
-
Strength assessment of SMART design against anticipated transient without scramChung, Young-Jong / Kim, Hyung-Rae / Chun, Ji-Han / Kim, Soo-Hyung / Bae, Kyoo-Hwan et al. | 2015
- 624
-
Computation of fundamental time-eigenvalue of the neutron transport equationShen, Huayun / Zhong, Bin / Liu, Huipo et al. | 2015
- 631
-
Potential application of a nanocomposite:HCNFe@polymer for effective removal of Cs (I) from nuclear wasteYousefi, Taher / Torab-Mostaedi, Meisam / Moosavian, Mohammad Ali / Mobtaker, Hossein Ghasemi et al. | 2015
- 640
-
Partitioned-Matrix acceleration to the Fission-Source iteration of the Variational Nodal MethodLi, Yunzhao / Wang, Yongping / Liang, Boning / Shen, Wei et al. | 2015
- 648
-
Optimization of neutron energy-group structure in thermal lattices using ultrafine bilinear adjoint functionFallah, Vahid Farhang / Salehi, Ali Akbar / Vosoughi, Naser / Akbari, Morteza et al. | 2015
- 659
-
Verification of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC by the PDS-XADS transient simulationWang, Gang / Gu, Zhixing / Wang, Zhen / Jin, Ming et al. | 2015
- 668
-
Review of the historic neutron noise behavior in German KWU built PWRsSeidl, Marcus / Kosowski, Kai / Schüler, Uwe / Belblidia, Lotfi et al. | 2015
- 676
-
Experimental study on the adsorption and desorption of tritium in the graphite materials for HTR-PMLi, Hong / Yang, Chen / Fang, Chao / Feng, Bingchen et al. | 2015
- 682
-
Thermal-hydraulic analysis of EBR-II Shutdown Heat Removal Tests SHRT-17 and SHRT-45RYue, Nina / Ma, Zaiyong / Cai, Rong / Hu, Benxue / Su, G.H. / Qiu, Suizheng et al. | 2015
- 694
-
Thermal-hydraulics analysis during fuel element failure in an operating PWRChen, Wenzhen / Yang, Lei / Xiao, Hongguang / Chen, Zhiyun et al. | 2015
- 701
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Development and verification of molten corium–concrete interaction codeLin, Bo / Qiu, S.Z. / Su, G.H. / Tian, W.X. / Zhang, Y.P. et al. | 2015
- 707
-
Analysis of the radiological contamination of the RBMK-1500 reactor low salted water systemPoskas, G. / Zujus, R. / Poskas, P. et al. | 2015
- 713
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Adsorption and immobilization of actinides using novel SiO2–ZrO2-calcium alginate aerogels from high level liquid wasteZhao, Junchuan / Ding, Xingeng / Meng, Cheng / Ren, Chunrong / Fu, Huiqin / Yang, Hui et al. | 2015
- 719
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Testing actinide fission yield treatment in CINDER90 for use in MCNP6 burnup calculationsFensin, Michael Lorne / Umbel, Marissa et al. | 2015
- 729
-
CFD based approach for modeling steam–water direct contact condensation in subcooled water flow in a tee junctionLi, S.Q. / Wang, P. / Lu, T. et al. | 2015
- 747
-
Numerical investigation of high level nuclear waste disposal in deep anisotropic geologic repositoriesSalama, Amgad / El Amin, Mohamed F. / Sun, Shuyu et al. | 2015
- 756
-
Numerical treatment for the point reactor kinetics equations using theta method, eigenvalues and eigenvectorsNahla, Abdallah A. et al. | 2015
- 764
-
Startup and burnup strategy for Th–U/U–Pu fuel cycles in an EM2 reactorMa, Y.W. / Li, X.X. / Cai, X.Z. / Yu, C.G. / Zou, C.Y. / Han, J.L. / Chen, J.G. et al. | 2015
- 771
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Experimental research on aerosols collection performance of self-priming venturi scrubber in FCVSZhou, Yanmin / Sun, Zhongning / Gu, Haifeng / Miao, Zhuang et al. | 2015
- IFC
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Editorial Board| 2015