Effect of dissolved hydrogen on corrosion of 316NG stainless steel in high temperature water (English)
- New search for: Dong, Lijin
- New search for: Peng, Qunjia
- New search for: Zhang, Zhiming
- New search for: Shoji, Tetsuo
- New search for: Han, En-Hou
- New search for: Ke, Wei
- New search for: Wang, Lei
- New search for: Dong, Lijin
- New search for: Peng, Qunjia
- New search for: Zhang, Zhiming
- New search for: Shoji, Tetsuo
- New search for: Han, En-Hou
- New search for: Ke, Wei
- New search for: Wang, Lei
In:
Nuclear Engineering and Design
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295
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403-414
;
2015
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Effect of dissolved hydrogen on corrosion of 316NG stainless steel in high temperature water
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Contributors:Dong, Lijin ( author ) / Peng, Qunjia ( author ) / Zhang, Zhiming ( author ) / Shoji, Tetsuo ( author ) / Han, En-Hou ( author ) / Ke, Wei ( author ) / Wang, Lei ( author )
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Published in:Nuclear Engineering and Design ; 295 ; 403-414
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Publisher:
- New search for: Elsevier B.V.
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Publication date:2015-08-30
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Size:12 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 295
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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Effect of complicated coolant flow behavior in the ABWR lower plenum on flow distribution to the coreWatanabe, Shun / Abe, Yutaka / Kaneko, Akiko / Watanabe, Fumitoshi / Tezuka, Kenichi / Hirao, Kazuki et al. | 2015
- 15
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Assessment study of RELAP5/SCDAP capability to reproduce TALL facility thermal hydraulic behaviorFiori, F. / Zhou, Z.W. et al. | 2015
- 27
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NPP planning based on analysis of ground vibration caused by collapse of large-scale cooling towersLin, Feng / Ji, Hongkui / Gu, Xianglin / Li, Yi / Wang, Mingreng / Lin, Tao et al. | 2015
- 40
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Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactorHeraltova, L. et al. | 2015
- 48
-
A porous medium model for predicting the duct wall temperature of sodium fast reactor fuel assemblyYu, Yiqi / Merzari, Elia / Obabko, Aleksandr / Thomas, Justin et al. | 2015
- 59
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Meso-scale modeling of irradiated concrete in test reactorGiorla, A. / Vaitová, M. / Le Pape, Y. / Štemberk, P. et al. | 2015
- 74
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Simulation of fuel dispersion in the MYRRHA-FASTEF primary coolant with CFD and SIMMER-IVBuckingham, Sophia / Planquart, Philippe / Eboli, Marica / Moreau, Vincent / Van Tichelen, Katrien et al. | 2015
- 84
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Core map generation for the ITU TRIGA Mark II research reactor using Genetic Algorithm coupled with Monte Carlo methodTürkmen, Mehmet / Çolak, Üner / Ergün, Şule et al. | 2015
- 96
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Structural behavior of SC panel subjected to impact loading using finite element analysisLee, Hyuk-Kee / Kim, Seung-Eock et al. | 2015
- 106
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Effect of hydrazine on general corrosion of carbon and low-alloyed steels in pressurized water reactor secondary side waterJärvimäki, Sari / Saario, Timo / Sipilä, Konsta / Bojinov, Martin et al. | 2015
- 116
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Development of the advanced mechanistic fuel performance and safety code using the multi-scale approachVeshchunov, M.S. / Boldyrev, A.V. / Kuznetsov, A.V. / Ozrin, V.D. / Seryi, M.S. / Shestak, V.E. / Tarasov, V.I. / Norman, G.E. / Kuksin, A.Yu. / Pisarev, V.V. et al. | 2015
- 127
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Evaluation of CANDU6 PCR (power coefficient of reactivity) with a 3-D whole-core Monte Carlo AnalysisMotalab, Mohammad Abdul / Kim, Woosong / Kim, Yonghee et al. | 2015
- 138
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Influence of the wet-well nodalization of a BWR3 Mark I on the containment thermal-hydraulic response during an SBO accidentHerranz, Luis E. / Fontanet, Joan / Fernández, Elena / López, Claudia et al. | 2015
- 148
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Heat transfer effect of an extended surface in downward-facing subcooled flow boilingKhan, Abdul R. / Erkan, Nejdet / Okamoto, Koji et al. | 2015
- 155
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Generalization of experimental data on amplitude and frequency of oscillations induced by steam injection into a subcooled poolVillanueva, Walter / Li, Hua / Puustinen, Markku / Kudinov, Pavel et al. | 2015
- 162
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Thermal–hydraulic numerical simulation of fuel sub-assembly using a dedicated meshing toolCadiou, Thierry / Saxena, Aakanksha et al. | 2015
- 173
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Convective heat transfer experiment of rod bundle flow with twist-vane spacer gridIn, Wang Kee / Shin, Chang Hwan / Lee, Chi Young et al. | 2015
- 182
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A Bayesian ensemble of sensitivity measures for severe accident modelingHoseyni, Seyed Mohsen / Di Maio, Francesco / Vagnoli, Matteo / Zio, Enrico / Pourgol-Mohammad, Mohammad et al. | 2015
- 192
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Dynamic rod worth simulation study for a sodium-cooled TRU burnerKim, Sang Ji / Ha, Pham Nhu Viet / Lee, Min Jae / Kang, Chang Mu et al. | 2015
- 204
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Sensitivity analysis of numerical model of prestressed concrete containmentBílý, Petr / Kohoutková, Alena et al. | 2015
- 215
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Incorporating single detector failure into the ROP detector layout optimization for CANDU reactorsKastanya, Doddy et al. | 2015
- 221
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TASS/SMR code improvement for small break LOCA applicability at an integral type reactor, SMARTChung, Young-Jong / Kim, Soo-Hyung / Lim, Sung-Won / Bae, Kyoo-Hwan et al. | 2015
- 228
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Analysis of accidents and abnormal transients of a high breeding fast reactor cooled by supercritical-pressure light waterGuo, Rui / Yamaji, Akifumi / Oka, Yoshiaki et al. | 2015
- 239
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A horizontal stratified gas–liquid two-phase flow model for the two-fluid model in the WCOBRA/TRAC-TF2 PWR safety analysis codeLiao, Jun / Ohkawa, Katsuhiro / Frepoli, Cesare et al. | 2015
- 251
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CFD simulations in heavy liquid metal flows for square lattice bare rod bundle geometries with a four parameter heat transfer turbulence modelManservisi, Sandro / Menghini, Filippo et al. | 2015
- 261
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Time and frequency domain analyses of the Hualien Large-Scale Seismic TestKabanda, John / Kwon, Oh-Sung / Kwon, Gunup et al. | 2015
- 276
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EDTA fouling in dead-end ultrafiltration of low level radioactive wastewaterNiu, Lixia / Zhang, Xue / Zhao, Xuan / Hu, Hongying et al. | 2015
- 283
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Branch-and-Bound algorithm applied to uncertainty quantification of a Boiling Water Reactor Station BlackoutNielsen, Joseph / Tokuhiro, Akira / Hiromoto, Robert / Tu, Lei et al. | 2015
- 305
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Laminar simulation of intersubchannel mixing in a triangular nuclear fuel bundle geometryZaretsky, A. / Lightstone, M.F. / Tullis, S. et al. | 2015
- 317
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Prediction of nucleate boiling heat transfer on horizontal U-shaped heat exchanger submerged in a pool of water using MARS codeJeon, Seong-Su / Hong, Soon-Joon / Cho, Hyoung-Kyu / Park, Goon-Cherl et al. | 2015
- 338
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Quantitative analysis of uncertainty from pebble flow in HTRChen, Hao / Fu, Li / Jiong, Guo / Ximing, Sun / Lidong, Wang et al. | 2015
- 346
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A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCAKim, Sang Ho / Chang, Soon Heung / Choi, Yu Jung / Jeong, Yong Hoon et al. | 2015
- 360
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Extended blackout mitigation strategy for PWRProšek, Andrej / Volkanovski, Andrija et al. | 2015
- 374
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Full-scale 3-D finite element modeling of a two-loop pressurized water reactor for heat transfer, thermal–mechanical cyclic stress analysis, and environmental fatigue life estimationMohanty, Subhasish / Soppet, William K. / Majumdar, Saurindranath / Natesan, Krishnamurti et al. | 2015
- 388
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Experimental characterisation of sprays resulting from impacts of liquid-containing projectilesHostikka, Simo / Silde, Ari / Sikanen, Topi / Vepsä, Ari / Paajanen, Antti / Honkanen, Markus et al. | 2015
- 403
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Effect of dissolved hydrogen on corrosion of 316NG stainless steel in high temperature waterDong, Lijin / Peng, Qunjia / Zhang, Zhiming / Shoji, Tetsuo / Han, En-Hou / Ke, Wei / Wang, Lei et al. | 2015
- 415
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Numerical analysis on inlet and outlet sections of a test fuel assembly for a Supercritical Water ReactorKiss, Attila / Vágó, Tamás / Aszódi, Attila et al. | 2015
- 429
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Development of sump model for containment hydrogen distribution calculations using CFD codeRavva, Srinivasa Rao / Iyer, Kannan N. / Gaikwad, A.J. et al. | 2015
- 441
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Investigation of station blackout scenario in VVER440/v230 with RELAP5 computer codeGencheva, Rositsa Veselinova / Stefanova, Antoaneta Emilova / Groudev, Pavlin Petkov et al. | 2015
- 457
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Structural integrity assessments of steam generator tubes using the FAD methodologyBergant, Marcos A. / Yawny, Alejandro A. / Perez Ipiña, Juan E. et al. | 2015
- 468
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Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear applicationAngelici Avincola, V. / Grosse, M. / Stegmaier, U. / Steinbrueck, M. / Seifert, H.J. et al. | 2015
- 479
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Analytical validation of operator actions in case of primary to secondary leakage for VVER-1000/V320Andreeva, M. / Groudev, P. / Pavlova, M. et al. | 2015
- 489
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Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport methodHe, Mingtao / Wu, Hongchun / Zheng, Youqi / Wang, Kunpeng / Li, Xunzhao / Zhou, Shengcheng et al. | 2015
- 500
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Release and redistribution of residual stress in the welded turbine rotor under service-type loadingsFeng, Lei / Xuan, Fu-zhen et al. | 2015
- 511
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Fully coupled multiphysics modeling of enhanced thermal conductivity UO2–BeO fuel performance in a light water reactorLiu, R. / Zhou, W. / Shen, P. / Prudil, A. / Chan, P.K. et al. | 2015
- 524
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Reducing the fuel temperature for pressure-tube supercritical-water-cooled reactors and the effect of fuel burnupNichita, E. / Kovaltchouk, V. et al. | 2015
- 534
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Structural effects of radiation-induced volumetric expansion on unreinforced concrete biological shieldsLe Pape, Y. et al. | 2015
- 549
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Counter flow induced draft cooling tower option for supercritical carbon dioxide Brayton cyclePidaparti, Sandeep R. / Moisseytsev, Anton / Sienicki, James J. / Ranjan, Devesh et al. | 2015
- 559
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Design of a PWR for long cycle and direct recycling of spent fuelMohamed, Nader M.A. et al. | 2015
- 567
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Stability, accuracy and numerical diffusion analysis of nodal expansion method for steady convection diffusion equationZhou, Xiafeng / Guo, Jiong / Li, Fu et al. | 2015
- 576
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Seismic fragility of RC shear walls in nuclear power plant Part 1: Characterization of uncertainty in concrete constitutive modelSyed, Sammiuddin / Gupta, Abhinav et al. | 2015
- 587
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Seismic fragility of RC shear walls in nuclear power plant part 2: Influence of uncertainty in material parameters on fragility of concrete shear wallsSyed, Sammiuddin / Gupta, Abhinav et al. | 2015
- 597
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Best papers from the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering| 2015
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- 615
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A fission matrix based validation protocol for computed power distributions in the advanced test reactorNielsen, Joseph W. / Nigg, David W. / LaPorta, Anthony W. et al. | 2015
- 625
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A modified Monte Carlo “Local Importance Function Transform” methodKeady, Kendra P. / Larsen, Edward W. et al. | 2015
- 632
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A spectral analysis of the domain decomposed Monte Carlo method for linear systemsSlattery, Stuart R. / Evans, Thomas M. / Wilson, Paul P.H. et al. | 2015
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Calculating infinite-medium α-eigenvalue spectra with Monte Carlo using a transition rate matrix methodBetzler, Benjamin R. / Kiedrowski, Brian C. / Brown, Forrest B. / Martin, William R. et al. | 2015
- 645
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