Personal information

Other IDs

ResearcherID: C-9973-2019

Keywords

Nuclear Engineering

Countries

United States

Activities

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Employment (4)

The Ohio State University: Columbus, Ohio, US

2018-09-01 to present | Associate Professor (Mechanical and Aerospace Engineering)
Employment
Source: Self-asserted source
Dean Wang

University of Massachusetts Lowell: Lowell, MA, US

2014-09-01 to 2018-08-31 | Associate Professor (Nuclear Engineeing Program)
Employment
Source: Self-asserted source
Dean Wang

Oak Ridge National Laboratory: Oak Ridge, TN, US

2010-12-22 to 2014-08-22 | R&D Staff (Reactor and Nuclear Systems Division)
Employment
Source: Self-asserted source
Dean Wang

Information Systems Laboratories (United States): Rockville, MD, US

2003-07-01 to 2010-12-20 | Sr. Scientist (Nuclear Ractor Analysis Division)
Employment
Source: Self-asserted source
Dean Wang

Education and qualifications (1)

Massachusetts Institute of Technology: Cambridge, MA, US

1999-09-01 to 2003-06-30 | Ph.D. (Nuclear Science and Engineering)
Education
Source: Self-asserted source
Dean Wang

Professional activities (1)

American Nuclear Society: La Grange Park, Illinois, US

1999 to present
Membership
Source: Self-asserted source
Dean Wang

Works (33)

High Order Asymptotic Preserving Hermite WENO Fast Sweeping Method for the Steady-State $$S_{N}$$ Transport Equations

Journal of Scientific Computing
2022-08-22 | Journal article
DOI: 10.1007/s10915-022-01965-x
Part of ISSN: 0885-7474
Part of ISSN: 1573-7691
Contributors: Dean Wang
Source: Self-asserted source
Dean Wang

Solving Neutron Transport K-Eigenvalue Problems Using the ANDO Method

2022 ANS Annual Meeting
2022-06 | Conference paper
Source: Self-asserted source
Dean Wang

Acceleration of Source Convergence in Monte Carlo Criticality Calculation with CMFD Schemes

PHYSOR 2022
2022-05 | Conference paper
Source: Self-asserted source
Dean Wang

An analytical nodal method for solving the SN transport equation in 2-D Cartesian geometry

Progress in Nuclear Energy
2022-05 | Journal article
DOI: 10.1016/j.pnucene.2022.104167
Part of ISSN: 0149-1970
Source: Self-asserted source
Dean Wang

Neutronic Design and Fuel Cycle Analysis of a Fluoride Salt-cooled High Temperature Reactor (FHR)

PHYSOR 2022
2022-05 | Conference paper
Source: Self-asserted source
Dean Wang

On a characteristic method for the SN neutron transport equation

Annals of Nuclear Energy
2021-12 | Journal article
DOI: 10.1016/j.anucene.2021.108670
Part of ISSN: 0306-4549
Source: Self-asserted source
Dean Wang

Neutron Transport Problems with Nonlinear Temperature Feedback

M&C2021
2021-10 | Conference paper
Source: Self-asserted source
Dean Wang

Solving Neutron Transport Problems with Sharp Boundary and Interior Layers Using the Shishkin Mesh

M&C2021
2021-10 | Conference paper
Source: Self-asserted source
Dean Wang

A New Proof of the Asymptotic Diffusion Limit of the SN Neutron Transport Equation

Nuclear Science and Engineering
2021-07-22 | Journal article
DOI: 10.1080/00295639.2021.1924048
Part of ISSN: 0029-5639
Part of ISSN: 1943-748X
Source: Self-asserted source
Dean Wang

Development of the reactor core isolation cooling system model for the extended station black-out accident

Nuclear Engineering and Design
2021-06 | Journal article
DOI: 10.1016/j.nucengdes.2021.111139
Part of ISSN: 0029-5493
Source: Self-asserted source
Dean Wang

Diffusion Theory for Inhomogeneous Neutron Transport Problems in Slab Geometry

ANS Virtual Annual Meeting
2021-06 | Conference paper
Source: Self-asserted source
Dean Wang

O-SRS: A Refueling and Shuffling Toolkit for Serpent Core Neutronics Analysis

ANS Virtual Annual Meeting
2021-06 | Conference paper
Source: Self-asserted source
Dean Wang

DEMONSTRATION OF A LINEAR PROLONGATION CMFD METHOD ON MOC

EPJ Web of Conferences
2021-01 | Journal article
DOI: 10.1051/epjconf/202124703006
Part of ISSN: 2100-014X
Source: Self-asserted source
Dean Wang

A Revisit to CMFD Schemes: Fourier Analysis and Enhancement

Energies
2021-01-14 | Journal article
DOI: 10.3390/en14020424
Part of ISSN: 1996-1073
Source: Self-asserted source
Dean Wang

Application of lpCMFD for K-Eigenvalue Transport Problems with Feedback

Transactions of the American Nuclear Society - Volume 123
2020-11 | Conference paper
DOI: 10.13182/t123-32990
Source: Self-asserted source
Dean Wang

Modeling and assessment of two-phase transonic steam flow with condensation through the convergent-divergent nozzle

Nuclear Engineering and Design
2020-08 | Journal article
DOI: 10.1016/j.nucengdes.2020.110632
Part of ISSN: 0029-5493
Source: Self-asserted source
Dean Wang

Enhancing lpCMFD Acceleration with Successive Overrelaxation for Neutron Transport Source Iteration

Nuclear Science and Engineering
2020-07-13 | Journal article
DOI: 10.1080/00295639.2020.1785190
Part of ISSN: 0029-5639
Part of ISSN: 1943-748X
Source: Self-asserted source
Dean Wang

A Novel Analytical Nodal Method for Solution of the SN Transport Equation

Transactions of the American Nuclear Society - Volume 122
2020-06 | Conference paper
DOI: 10.13182/t122-31951
Source: Self-asserted source
Dean Wang

RELAP-7 Application and Enhancement for FLEX Strategies and ATF Behavior under Extended Loss of AC Power Conditions

[]
2020-04-30 | Report
DOI: 10.2172/1616543
Source: Self-asserted source
Dean Wang

The Asymptotic Diffusion Limit of Numerical Schemes for the SN Transport Equation

Nuclear Science and Engineering
2019-12-02 | Journal article
DOI: 10.1080/00295639.2019.1638660
Part of ISSN: 0029-5639
Part of ISSN: 1943-748X
Source: Self-asserted source
Dean Wang

Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing

Nuclear Technology
2019-09-02 | Journal article
DOI: 10.1080/00295450.2019.1586372
Part of ISSN: 0029-5450
Part of ISSN: 1943-7471
Source: Self-asserted source
Dean Wang

High-Order Lax-Friedrichs WENO Fast Sweeping Methods for the SN Neutron Transport Equation

Nuclear Science and Engineering
2019-09-02 | Journal article
DOI: 10.1080/00295639.2019.1582316
Part of ISSN: 0029-5639
Part of ISSN: 1943-748X
Source: Self-asserted source
Dean Wang

Development of a Novel Accelerator for Neutron Transport Solution Using the Galerkin Spectral Element Methods (Final Report)

[]
2019-04-30 | Report
DOI: 10.2172/1511575
Source: Self-asserted source
Dean Wang

A Coarse-Mesh Diffusion Synthetic Acceleration Method with Local hp Adaptation for Neutron Transport Calculations

Nuclear Science and Engineering
2018-11-02 | Journal article
DOI: 10.1080/00295639.2018.1499338
Part of ISSN: 0029-5639
Part of ISSN: 1943-748X
Source: Self-asserted source
Dean Wang

A Linear Prolongation Approach to Stabilizing CMFD

Nuclear Science and Engineering
2018-04-03 | Journal article
DOI: 10.1080/00295639.2017.1417347
Part of ISSN: 0029-5639
Part of ISSN: 1943-748X
Source: Self-asserted source
Dean Wang

A Local Adaptive Coarse-Mesh Nonlinear Diffusion Acceleration Scheme for Neutron Transport Calculations

Nuclear Science and Engineering
2018-03-04 | Journal article
DOI: 10.1080/00295639.2017.1394088
Part of ISSN: 0029-5639
Part of ISSN: 1943-748X
Source: Self-asserted source
Dean Wang

Thermal hydraulics analysis of the Advanced High Temperature Reactor

Nuclear Engineering and Design
2015-12 | Journal article
DOI: 10.1016/j.nucengdes.2015.08.017
Part of ISSN: 0029-5493
Source: Self-asserted source
Dean Wang

Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions

Journal of Nuclear Materials
2014-05 | Journal article
DOI: 10.1016/j.jnucmat.2013.09.052
Part of ISSN: 0022-3115
Source: Self-asserted source
Dean Wang

The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents

Journal of Nuclear Materials
2014-05 | Journal article
DOI: 10.1016/j.jnucmat.2013.09.051
Part of ISSN: 0022-3115
Source: Self-asserted source
Dean Wang

Implementation and assessment of high-resolution numerical methods in TRACE

Nuclear Engineering and Design
2013-10 | Journal article
DOI: 10.1016/j.nucengdes.2013.05.015
Part of ISSN: 0029-5493
Source: Self-asserted source
Dean Wang

Cross Section Generation Guidelines for TRACE-PARCS

2013-06 | Report
Source: Self-asserted source
Dean Wang

Study of Fukushima Daiichi Nuclear Power Station Unit 4 Spent-Fuel Pool

Nuclear Technology
2012-11 | Journal article
DOI: 10.13182/nt12-a14634
Part of ISSN: 0029-5450
Part of ISSN: 1943-7471
Source: Self-asserted source
Dean Wang

Fukushima Daiichi Accident Study

2012-07 | Report
Source: Self-asserted source
Dean Wang
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