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(n.d.) Nuclear Engineering and Design Vol. 353. Elsevier BV

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Reference TypeJournal (volume)
JournalNuclear Engineering and Design
PublisherElsevier BV
Mindat Ref. ID10515863Long-form Identifiermindat:1:5:10515863:1
GUID0
Full Reference(n.d.) Nuclear Engineering and Design Vol. 353. Elsevier BV
Plain Text(n.d.) Nuclear Engineering and Design Vol. 353. Elsevier BV
InElsevier BV - Nuclear Engineering and Design

Contains

Chen, Zhong, Zhao, Zijia, Lv, Zhongliang, Ma, Yanyun (2019) Coaxial stacking disjoint model study of 10 MW high temperature gas-cooled reactor (HTR-10). Nuclear Engineering and Design, 353. 110193pp. doi:10.1016/j.nucengdes.2019.110193
Räty, Antti, Lavonen, Tiina, Leskinen, Anumaija, Likonen, Jari, Postolache, Cristian, Fugaru, Viorel, Bubueanu, George, Lungu, Cristian, Bucsa, Adrian (2019) Characterization measurements of fluental and graphite in FiR1 TRIGA research reactor decommissioning waste. Nuclear Engineering and Design, 353. 110198pp. doi:10.1016/j.nucengdes.2019.110198
Chen, Shengli, Bernard, David (2019) Attenuation of atomic displacement damage in the heavy reflector of the PERLE experiment and application to EPR. Nuclear Engineering and Design, 353. 110205pp. doi:10.1016/j.nucengdes.2019.110205
You, Byung-Hyun, Jeong, Yong Hoon, Addad, Yacine (2019) Assessment of advanced RANS models ability to predict a turbulent swept liquid metal flow over a wire in a channel. Nuclear Engineering and Design, 353. 110206pp. doi:10.1016/j.nucengdes.2019.110206
Qu, Wenhai, Wang, Zefeng, Xiong, Jinbiao, Cheng, Xu (2019) Experimental study of cross flow and lateral pressure drop in a 5 × 5 rod bundle with mixing vane spacer grid. Nuclear Engineering and Design, 353. 110209pp. doi:10.1016/j.nucengdes.2019.110209
Angeli, P.-E. (2019) Verification and validation of LES of a triple parallel jet flow in the context of a thermal striping investigation. Nuclear Engineering and Design, 353. 110210pp. doi:10.1016/j.nucengdes.2019.110210
Busco, Giacomo, Hassan, Yassin A. (2019) Solution verification of PANS model for a PWR fuel assembly. Nuclear Engineering and Design, 353. 110213pp. doi:10.1016/j.nucengdes.2019.110213
Marinari, R., Di Piazza, I., Tarantino, M., Forgione, N. (2019) Blockage fuel pin simulator experiments and simulation. Nuclear Engineering and Design, 353. 110215pp. doi:10.1016/j.nucengdes.2019.110215
Gutowska, Izabela, Woods, Brian G., Cadell, Seth R. (2019) CFD modeling of the OSU High Temperature Test Facility inlet plenum flow distribution during normal operation. Nuclear Engineering and Design, 353. 110216pp. doi:10.1016/j.nucengdes.2019.110216
Li, Yanhui, Jiang, Jin (2019) Reliability evaluation of secondary support structure in hypothetical drop of reactor core barrel assembly. Nuclear Engineering and Design, 353. 110219pp. doi:10.1016/j.nucengdes.2019.110219
Shams, A., De Santis, A., Koloszar, L.K., Villa Ortiz, A., Narayanan, C. (2019) Status and perspectives of turbulent heat transfer modelling in low-Prandtl number fluids. Nuclear Engineering and Design, 353. 110220pp. doi:10.1016/j.nucengdes.2019.110220
Moreau, V., Profir, M., Keijers, S., Van Tichelen, K. (2019) An improved CFD model for a MYRRHA based primary coolant loop. Nuclear Engineering and Design, 353. 110221pp. doi:10.1016/j.nucengdes.2019.110221
Dolganov, Kirill S., Semenov, Vladimir N., Kiselev, Arkady Ye., Tomashchik, Dmitry Yu., Fokin, Alexey L., Astakhov, Valery V., Nikolaeva, Anna V., Gasparov, Dmitry L., Pantyushin, Stanislav I., Bukin, Nikolay V., Bykov, Mikhail A. (2019) Evaluation of loads on the main joint of reactor pressure vessel under hypothetical severe accident at VVER-1200 NPP. Nuclear Engineering and Design, 353. 110222pp. doi:10.1016/j.nucengdes.2019.110222
Goda, Raito, Hayashi, Kosuke, Murase, Michio, Hosokawa, Shigeo, Tomiyama, Akio (2019) Experimental study on interfacial and wall friction factors under counter-current flow limitation in vertical pipes with sharp-edged lower ends. Nuclear Engineering and Design, 353. 110223pp. doi:10.1016/j.nucengdes.2019.110223
Yin, Tingru, Lu, Daogang, Huang, Yijun, Liu, Yu (2019) Study on added mass model for fluid-structure interaction of spent fuel storage rack. Nuclear Engineering and Design, 353. 110224pp. doi:10.1016/j.nucengdes.2019.110224
Dolfen, H., Bertocchi, F., Rohde, M., Degroote, J. (2019) Vibrations in a 7-rod bundle subject to axial flow: Simulations and experiments. Nuclear Engineering and Design, 353. 110227pp. doi:10.1016/j.nucengdes.2019.110227
Dzodzo, Milorad (2019) Scaling analysis and relation to EMDAP and BEPU. Nuclear Engineering and Design, 353. 110228pp. doi:10.1016/j.nucengdes.2019.110228
Gelain, Thomas, Alengry, Jonathan, Vauquelin, Olivier, Ricciardi, Laurent (2019) Tracer dispersion in a duct: Experimental and numerical approach – Application to the well-mixing length determination. Nuclear Engineering and Design, 353. 110229pp. doi:10.1016/j.nucengdes.2019.110229
Palomino, Luis M., El-Genk, Mohamed S. (2019) Friction factor correlation for hexagonal bundles of bare tubes/rods and with flat and scalloped walls. Nuclear Engineering and Design, 353. 110230pp. doi:10.1016/j.nucengdes.2019.110230
Villa Ortiz, Agustín, Koloszar, Lilla, Planquart, Philippe (2019) Large Eddy Simulations on a natural convection boundary layer at Pr = 0.71 and 0.025. Nuclear Engineering and Design, 353. 110231pp. doi:10.1016/j.nucengdes.2019.110231
Zheng, Guiqiu, Carpenter, David, Dolan, Kieran, Hu, Lin-wen (2019) Experimental investigation of alumina coating as tritium permeation barrier for molten salt nuclear reactors. Nuclear Engineering and Design, 353. 110232pp. doi:10.1016/j.nucengdes.2019.110232
Leskovar, Matjaž, Centrih, Vasilij, Uršič, Mitja, Kokalj, Janez (2019) Investigation of steam explosion duration in stratified configuration. Nuclear Engineering and Design, 353. 110233pp. doi:10.1016/j.nucengdes.2019.110233
Nguyen, Thien, White, Lance, Vaghetto, Rodolfo, Hassan, Yassin (2019) High-fidelity velocity measurements in a totally blocked interior subchannel of a wire-wrapped 61-pin hexagonal fuel bundle. Nuclear Engineering and Design, 353. 110234pp. doi:10.1016/j.nucengdes.2019.110234
Shen, Danhong, Liu, Xiaojing, Cheng, Xu (2019) A study on geometric shape factors for turbulent mixing coefficents in rod bundles. Nuclear Engineering and Design, 353. 110235pp. doi:10.1016/j.nucengdes.2019.110235
Mora, Diego F., Niffenegger, Markus, Qian, Guian, Jaros, Michal, Niceno, Bojan (2019) Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM. Nuclear Engineering and Design, 353. 110237pp. doi:10.1016/j.nucengdes.2019.110237
Zhang, Kanglong, Sanchez-Espinoza, Victor Hugo (2019) Optimization and verification of the coupled code TRACE/SubChanFlow using the VVER-1000 coolant mixing benchmark data. Nuclear Engineering and Design, 353. 110238pp. doi:10.1016/j.nucengdes.2019.110238
Kelm, Stephan, MĂĽller, Henrik, Hundhausen, Alexander, Druska, Claudia, Kuhr, Astrid, Allelein, Hans-Josef (2019) Development of a multi-dimensional wall-function approach for wall condensation. Nuclear Engineering and Design, 353. 110239pp. doi:10.1016/j.nucengdes.2019.110239
Aoyagi, Mitsuhiro, Uchibori, Akihiro, Kikuchi, Shin, Takata, Takashi, Ohno, Shuji, Ohshima, Hiroyuki (2019) Identification of important phenomena through the PIRT process for development of sodium fire analysis codes. Nuclear Engineering and Design, 353. 110240pp. doi:10.1016/j.nucengdes.2019.110240
Wang, Dayang, Zhang, Yongshan, Wu, Chengqing, Xue, Guofeng, Huang, Wencheng (2019) Seismic performance of base-isolated AP1000 shield building with consideration of fluid-structure interaction. Nuclear Engineering and Design, 353. 110241pp. doi:10.1016/j.nucengdes.2019.110241
Yaman, Onur, Koksal, Murat, Kulah, Gorkem (2019) Comment on “Deciphering conical spouted bed hydrodynamics using high intensity microphone”. Nuclear Engineering and Design, 353. 110242pp. doi:10.1016/j.nucengdes.2019.110242
Novak, Ondrej, Sklenka, Lubomir, Huml, Ondrej, Frybort, Jan, Chvala, Ondrej, Luciano, Nicholas P., Maldonado, G. Ivan (2019) Benchmark evaluation of zero-power critical parameters for the Temelin VVER nuclear reactor using SERPENT & NESTLE and MCNP. Nuclear Engineering and Design, 353. 110243pp. doi:10.1016/j.nucengdes.2019.110243
Wibisono, Andhika Feri, Lee, Jeong Ik, Shwageraus, Eugene (2019) Effect of operating pressure on the performance of a hybrid system of small modular boiling water reactor with external superheaters. Nuclear Engineering and Design, 353. 110244pp. doi:10.1016/j.nucengdes.2019.110244
Zhang, Lu, Yang, Yongwei, Ma, Fei, Zhou, Qi, Gu, Long, Zhu, Qingfu, Gao, Yucui, Li, Jinyang, Yu, Rui, Jiang, Wei (2019) Deterministic simulation of the static neutronic characteristics for the lead core of VENUS-II facility. Nuclear Engineering and Design, 353. 110258pp. doi:10.1016/j.nucengdes.2019.110258
Lorusso, P., Pesetti, A., Barone, G., Castelliti, D., Caruso, G., Forgione, N., Giannetti, F., Martelli, D., Rozzia, D., Van Tichelen, K., Tarantino, M. (2019) MYRRHA primary heat exchanger experimental simulations on CIRCE-HERO. Nuclear Engineering and Design, 353. 110270pp. doi:10.1016/j.nucengdes.2019.110270
Narcisi, V., Giannetti, F., Del Nevo, A., Alcaro, F., Wang, X., Kraus, A., Brunett, A., Thomas, J., Girault, N., Grosjean, B., Caruso, G., Gerschenfeld, A. (2019) System thermal-hydraulic modelling of the phénix dissymmetric test benchmark. Nuclear Engineering and Design, 353. 110272pp. doi:10.1016/j.nucengdes.2019.110272
Roelofs, Ferry, Uitslag-Doolaard, Heleen, Dovizio, Daniele, Mikuz, Blaz, Shams, Afaque, Bertocchi, Fulvio, Rohde, Martin, Pacio, Julio, Di Piazza, Ivan, Kennedy, Graham, Van Tichelen, Katrien, Obabko, Aleks, Merzari, Elia (2019) Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly. Nuclear Engineering and Design, 353. 110273pp. doi:10.1016/j.nucengdes.2019.110273
Shams, A., Roelofs, F., Niceno, B., Guo, W., Angeli, D., Stalio, E., Fregni, A., Duponcheel, M., Bartosiewicz, Y., Tiselj, I., Oder, J. (2019) Reference numerical database for turbulent flow and heat transfer in liquid metals. Nuclear Engineering and Design, 353. 110274pp. doi:10.1016/j.nucengdes.2019.110274
Hong, Kisik, Barber, J.R., Thouless, M.D., Lu, Wei (2019) Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions. Nuclear Engineering and Design, 353. 110275pp. doi:10.1016/j.nucengdes.2019.110275
He, Yanan, Shirvan, Koroush, Wu, Yingwei, Su, G.H. (2019) Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions. Nuclear Engineering and Design, 353. 110276pp. doi:10.1016/j.nucengdes.2019.110276
Zwijsen, K., Dovizio, D., Moreau, V., Roelofs, F. (2019) CFD modelling of the CIRCE facility. Nuclear Engineering and Design, 353. 110277pp. doi:10.1016/j.nucengdes.2019.110277
Mathur, Akshat, Uitslag-Doolaard, Heleen, Roelofs, Ferry (2019) Reduced RANS approach validation to model passive heat removal due to inter-wrapper flow. Nuclear Engineering and Design, 353. 110278pp. doi:10.1016/j.nucengdes.2019.110278
Forgione, N., Martelli, D., Barone, G., Giannetti, F., Lorusso, P., Hollands, T., Papukchiev, A., Polidori, M., Cervone, A., Di Piazza, I. (2019) Post-test simulations for the NACIE-UP benchmark by STH codes. Nuclear Engineering and Design, 353. 110279pp. doi:10.1016/j.nucengdes.2019.110279
Christian, Robby, Lee, Youho, Kang, Hyun Gook (2019) Emergency core cooling system performance criteria for Multi-Layered Silicon Carbide nuclear fuel cladding. Nuclear Engineering and Design, 353. 110280pp. doi:10.1016/j.nucengdes.2019.110280
Toptan, Aysenur, Kropaczek, David J., Avramova, Maria N. (2019) Gap conductance modeling I: Theoretical considerations for single- and multi-component gases in curvilinear coordinates. Nuclear Engineering and Design, 353. 110283pp. doi:10.1016/j.nucengdes.2019.110283
Zhang, K., You, H.B., Zhou, Y.K., Zhao, X.H., Zhang, J., Hou, Y.D., Tian, W.X., Su, G.H., Qiu, S.Z. (2019) Experimental investigations on leak flow rate characteristics of water through axial artificial microcracks of steam generator tubes under back pressure conditions. Nuclear Engineering and Design, 353. 110285pp. doi:10.1016/j.nucengdes.2019.110285
Kauppinen, Otso-Pekka, Kouhia, Virpi, Riikonen, Vesa, Hyvärinen, Juhani (2019) System code analysis of accumulator nitrogen discharge during LOCA experiment at PWR PACTEL test facility. Nuclear Engineering and Design, 353. 110288pp. doi:10.1016/j.nucengdes.2019.110288
Gorton, Jacob P., Lee, Soon K., Lee, Youho, Brown, Nicholas R. (2019) Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties. Nuclear Engineering and Design, 353. 110295pp. doi:10.1016/j.nucengdes.2019.110295
(2019) Editorial Board. Nuclear Engineering and Design, 353. 110329pp. doi:10.1016/s0029-5493(19)30364-4

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