A surrogate model based on sparse grid interpolation for boiling water reactor subchannel void distribution (2024)

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

Neutronic simulations for the FRM II

Reiter, C. / Breitkreutz, H. / Röhrmoser, A. / Seubert, A. / Petry, W. et al. | 2019

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9

Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5

Park, Jinsu / Kim, Wonkyeong / Hursin, Mathieu / Perret, Gregory / Vasiliev, Alexander / Rochman, Dimitri / Pautz, Andreas / Ferroukhi, Hakim / Lee, Deokjung et al. | 2019

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23

Assessment of different turbulence models on the large scale internal heated water pool natural convection simulation

Wei, Hongyang / Chen, Yitung et al. | 2019

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39

Long-term decay heat removal in a submerged SMR

Santinello, Marco / Ricotti, Marco et al. | 2019

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51

A surrogate model based on sparse grid interpolation for boiling water reactor subchannel void distribution

Bennett, Alexander / Martin, Nicolas / Avramova, Maria et al. | 2019

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63

Experimental investigation of the nonlinear pressure fluctuations in a residual heat removal pump

Pei, Ji / Wang, Wenjie / Pavesi, Giorgio / Osman, Majeed Koranteng / Meng, Fan et al. | 2019

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80

Experimental study on the resistance characteristics of the rod bundle channel with spacer grid under low-frequency pulsating flows

Qi, Peiyao / Li, Xing / Li, Xin / Qiao, Shouxu / Tan, Sichao / Chen, Yitung et al. | 2019

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93

A simulated experimental study on eutectic reaction of core materials using Pb-Sn couple

Xiong, Zhihong / Cheng, Songbai / Sun, Yubo / Huang, Lili / Wang, Na / Wen, Junlang et al. | 2019

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102

A hybrid method for reactor core simulations employing finite difference and polynomial expansion with improved treatment of transverse leakage

Ray, Sherly / Degweker, S.B. / Kannan, Umasankari et al. | 2019

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112

Numerical analysis of criticality of fuel debris falling in water

Muramoto, Takeshi / Nishiyama, Jun / Obara, Toru et al. | 2019

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123

Application of droplet motion and phase change model in containment spray system

Zhao, Fulong / Yan, Xiao / Bo, Hanliang / Meng, Tao / Zeng, Chen / Tan, Sichao et al. | 2019

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138

Calculation of the cross and auto power spectral densities for low neutron counting from pulse mode detectors

Talamo, Alberto / Gohar, Yousry / Yamamoto, Toshihiro / Yamanaka, Masao / Pyeon, Cheol Ho et al. | 2019

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148

Predictions of quench temperature and quench velocity in narrow rectangular channel of novel plate-type reactor

Xu, Wei / Guo, Jiuyuan / Liu, Xiaojing / Xiong, Jinbiao / Chai, Xiang / Zhang, Tengfei / Cheng, Xu / Zeng, Wei et al. | 2019

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156

Development of phenomena identification ranking table for LONF-ATWS sequences in a Westinghouse PWR

Rebollo, María José / Queral, César / Fernández-Cosials, Kevin / Sánchez-Torrijos, Jorge / Posada, José María et al. | 2019

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171

Visual investigation on the boiling crisis post the flow instability in the channel with bypass

Lu, Qi / Liu, Yu / Huang, Huijian / Shen, Caifen / He, Hangxing / Zhou, Linglan / Chen, Deqi et al. | 2019

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185

Effects of ocean motions on density wave oscillations under natural circulation

Wang, Sipeng / Yang, Bao-Wen et al. | 2019

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196

Experimental study on boiling heat transfer in a three-rod bundle at near-critical pressure

Chen, Shuo / Xiao, Yao / Gu, Hanyang et al. | 2019

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210

Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors

Zhang, Tengfei / Xiong, Jinbiao / Liu, Luguo / Li, Zhipeng / Zhuang, Kun et al. | 2019

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221

Experimental study of velocity components of low-RE pulsatile flow through bare rod bundle

Ala, Ayodeji A. / Tan, Sichao / Eltayeb, Abdelgadir / Mi, Zhengpeng et al. | 2019

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233

Development of Anti-windup PI Control and Bumpless Control Transfer Methodology for Feedwater Control System

Tran, Thanh Cong / Jung, Jae Cheon et al. | 2019

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242

Fragility analysis of prestressed concrete containment under severe accident condition

Jin, Song / Li, Zhongcheng / Lan, Tianyun / Gong, Jinxin et al. | 2019

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257

Implementation and performance analysis of the massively parallel method of characteristics based on GPU

Song, Peitao / Zhang, Zhijian / Liang, Liang / Zhang, Qian / Zhao, Qiang et al. | 2019

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273

Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review

Deng, Chengcheng / Zhang, Xueyan / Yang, Ye / Yang, Jun et al. | 2019

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291

Consideration of H2 generation in fluid governing equations of SPACE code

Ha, Kwi Seok / Lee, Seung Wook / Kim, Kyung Doo et al. | 2019

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297

Monte Carlo fuel burnup analyses of the Accelerator-Driven Subcritical systems

Cao, Yan / Gohar, Yousry et al. | 2019

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305

Observation of dissolved gas separation and accumulation in stationary water

Jo, Hongrae / Song, Yong Jae / Jo, Daeseong et al. | 2019

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317

Molecular dynamics modelling of the thermal conductivity of off-stoichiometric UO2±x and (UyPu1−y)O2±x using equilibrium molecular dynamics

Maxwell, Christopher I. / Pencer, Jeremy et al. | 2019

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325

Signature selection for the identification of unknown spent nuclear fuel samples

Su, Jiahang / Wu, Jun / Hu, Side et al. | 2019

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332

Accurate full superfine group resonance self-shielding method with fission source and upscattering effects in thermal lattice

Safarzadeh, O. et al. | 2019

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344

Study on shaft-block under small break loss of coolant accident of nuclear main pump

Wang, Xiuli / Liu, Yong / Zhu, Rongsheng et al. | 2019

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353

Exact perturbation theory for fusion blanket design

Jolodosky, Alejandra / Aufiero, Manuele / Fratoni, Massimiliano et al. | 2019

digital version

367

A design-phase probabilistic safety assessment of a research reactor to enhance its safety

Lee, Yoon-Hwan et al. | 2019

digital version

378

An approach for determining reasonable sample sizes of MARSSIM final status surveys in decommissioning of nuclear facilities

Sohn, Wook / Seo, Hyung-Woo / Jeong, Kahee et al. | 2019

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385

A summary of the ARTIST: Aerosol retention during SGTR severe accident

Lind, Terttaliisa / Guentay, Salih / Herranz, Luis E. / Suckow, Detlef et al. | 2019

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401

An experimental study on natural circulation flow characteristics under passive IVR-ERVC conditions

Wang, Fan / Kuang, Bo / Liu, Pengfei / Zhu, Chen et al. | 2019

digital version

412

Self-sintered nanopore-isotropic graphite derived from green pitch coke for application in molten salt nuclear reactor

Zhao, Hongchao / He, Zhao / Liu, Zhanjun / Song, Jinliang / Tsang, D.K.L. / Zhang, Heyao et al. | 2019

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417

Proper orthogonal decomposition based online power-distribution reconstruction method

Li, Zhuo / Ma, Yu / Cao, Liangzhi / Wu, Hongchun et al. | 2019

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425

Forced reflood modeling in a 2 × 2 rod bundle with a 90% partially blocked region

Hashemi-Tilehnoee, Mehdi / Tashakor, Saman / Seyyedi, Seyyed Masoud / Sahebi, Neda et al. | 2019

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433

An adaptive probabilistic mapping matrix search algorithm for vulnerability analysis of PPS

Yang, Jun / Wang, Jun / Wei, Guanxiang / Yang, Ming / Lu, Hongxing et al. | 2019

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443

Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD

Park, Ho Jin / Kang, Hyunwook / Lee, Hyun Chul / Cho, Jin Young et al. | 2019

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460

Analysis of air-steam condensation tests on a vertical tube of the passive containment cooling system under natural convection

Lee, Yeon-Gun / Jang, Yeong-Jun / Kim, Sin et al. | 2019

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475

Neutron noise analysis using the basic element method

Korepanova, N.V. / Dikusar, N.D. / Pepelyshev, Y.N. / Dima, M. et al. | 2019

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483

Multiphysics simulation of moisture-graphite oxidation in MHTGR

Wang, Chengqi / Sun, Xiaodong / Christensen, Richard N. et al. | 2019

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496

Novel consistent approach in controllability evaluations of point reactor kinetics models

Luan, Xiuchun / Tsvetkov, Pavel V. et al. | 2019

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ii

Editorial Board

| 2019

digital version

A surrogate model based on sparse grid interpolation for boiling water reactor subchannel void distribution (2024)
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