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在“Elsevier电子期刊”中，命中：9条，耗时：0.0409738 秒

在所有数据库中总计命中：46条

1.Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis

作者：Robert Montgomery^a ; ^{robert.montgomery@pnnl.gov" class="auth_mail" title="E-mail the corresponding author} ; Carlos Tomé ; ^b ; ^{tome@lanl.gov" class="auth_mail" title="E-mail the corresponding author} ; Wenfeng Liu^c ; ^{wenfeng.liu@anatech.com" class="auth_mail" title="E-mail the corresponding author} ; Alankar Alankar^d ; ^{alankar.alankar@iitb.ac.in" class="auth_mail" title="E-mail the corresponding author} ; Gopinath Subramanian^e ; ^{gopinath.subramanian@usm.edu" class="auth_mail" title="E-mail the corresponding author} ; Christopher Stanek^b ; ^{stanek@lanl.gov" class="auth_mail" title="E-mail the corresponding author}

关键词：Nuclear fuel modeling ; Microstructure deformation modeling ; Zirconium alloy ; Irradiation growth ; Irradiation creep ; Plasticity

刊名：Journal of Computational Physics

出版年：2017

2.Modeling and simulation challenges pursued by the Consortium for Advanced Simulation of Light Water Reactors (CASL)

作者：Paul J. Turinsky^a ; ^{turinsky@ncsu.edu" class="auth_mail" title="E-mail the corresponding author} ; Douglas B. Kothe^b ; ^{kothe@ornl.gov" class="auth_mail" title="E-mail the corresponding author}

关键词：Modeling ; Simulation ; Core simulator ; Multiphysics ; Nuclear energy

刊名：Journal of Computational Physics

出版年：2016

3.Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event

作者：C.S. Brown^a ; ^{csbrown3@ncsu.edu" class="auth_mail" title="E-mail the corresponding author} ; H. Zhang^b ; ^{Hongbin.Zhang@inl.gov" class="auth_mail" title="E-mail the corresponding author} ; V. Kucukboyaci^c ; ^{kucukbvn@westinghouse.com" class="auth_mail" title="E-mail the corresponding author} ; Y. Sung^c ; ^{sungy@westinghouse.com" class="auth_mail" title="E-mail the corresponding author}

关键词：BEPU ; best estimate plus uncertainty ; CASL ; Consortium for Advanced Simulation of Light Water Reactors ; CC ; correlation coefficient ; CFD ; computational fluid dynamics ; CHF ; critical heat flux ; CTF ; COBRA-TF ; DNB ; departure from nucleate boiling ; DNBR ; departure from nucleate boiling ratio ; EOC ; end of cycle ; FOM ; figure of merit ; HF ; high flow ; HFP ; hot full power ; HPC ; high performance computing ; HZP ; hot zero power ; INL ; Idaho National Laboratory ; LF ; low flow ; LOCA ; loss-of-coolant accident

刊名：Nuclear Engineering and Design

出版年：2016

4.Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport code

作者：Tara M. Pandya ; ¹ ; ^{pandyatm@ornl.gov" class="auth_mail" title="E-mail the corresponding author} ; Seth R. Johnson¹ ; ^{johnsonsr@ornl.gov" class="auth_mail" title="E-mail the corresponding author} ; Thomas M. Evans¹ ; ^{evanstm@ornl.gov" class="auth_mail" title="E-mail the corresponding author} ; Gregory G. Davidson¹ ; ^{davidsongg@ornl.gov" class="auth_mail" title="E-mail the corresponding author} ; Steven P. Hamilton¹ ; ^{hamiltonsp@ornl.gov" class="auth_mail" title="E-mail the corresponding author} ; Andrew T. Godfrey² ; ^{godfreyat@ornl.gov" class="auth_mail" title="E-mail the corresponding author}

关键词：Monte Carlo methods ; Neutron transport ; Parallel computation

刊名：Journal of Computational Physics

出版年：2016

5.The Virtual Environment for Reactor Applications (VERA): Design and architecture^☆

作者：John A. Turner^a ; ^{turnerja@ornl.gov" class="auth_mail" title="E-mail the corresponding author} ; Kevin Clarno^a ; Matt Sieger^a ; Roscoe Bartlett^a ; Benjamin Collins^a ; Roger Pawlowski^b ; Rodney Schmidt^b ; Randall Summers^b

关键词：Nuclear reactor ; Modeling ; Simulation ; Coupled physics ; Multiphysics ; Core simulator ; Neutronics ; Fluid flow ; Thermal-hydraulics

刊名：Journal of Computational Physics

出版年：2016

6.Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT

关键词：2D/1D method ; MOC ; MPACT

刊名：Journal of Computational Physics

出版年：2016

7.Uncertainty quantification and sensitivity analysis with CASL Core Simulator VERA-CS

作者：C.S. Brown^a ; ^{csbrown3@ncsu.edu" class="auth_mail" title="E-mail the corresponding author} ; Hongbin Zhang^b ; ^{Hongbin.Zhang@inl.gov" class="auth_mail" title="E-mail the corresponding author}

关键词：CASL ; VERA-CS ; Uncertainty quantification ; Sensitivity analysis

刊名：Annals of Nuclear Energy

出版年：2016

8.Turbulent flow characteristics in an annulus under air bubble injection and subcooled flow boiling conditions

作者：R. Samaroo ; N. Kaur ; K. Itoh ; T. Lee ; S. Banerjee ; M. Kawaji

刊名：Nuclear Engineering and Design

出版年：March, 2014

9.Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors

作者：J. Bakosi ; M.A. Christon ; R.B. Lowrie ; L.A. Pritchett-Sheats ; R.R. Nourgaliev

刊名：Nuclear Engineering and Design

出版年：2013

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