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FynanDouglas
Fynan, Douglas A.

FynanDouglas

원자력공학과

  • Nuclear Science, Simulation & Safety Lab.
  • Website
Research Interests
Nuclear Science;Reactor Physics;Dynamic PSA;Nuclear Engineering;원자력 과학;노물리;확률론적 안전성 평가;열수력;원자로안전학;원자력공학
Lab Description
The NSSS is an experimental lab to develop robust methodologies for rigorous treatment of uncertainties, identification of biases, and improved physics modeling for the evolving needs of the reactor physics and thermal-hydraulic fields. Target applications of the methodologies include reactor physics, BEPU, severe accident simulation, passive safety system assessment and design optimization. NSSS lab also explores new and innovative uses of nuclear science and technology including particle accelerator applications, alternative reactor coolants, and nuclear forensic techniques in nuclear nonproliferation.
Researcher ID Research Gate ORCiD Scopus Google Scholar
Previous
Activated sodium adjuster rod design for enhanced delayed-photoneutron yield in heavy water reactors File

Seo, Yeseul , Hakim, Arief Rahman , Setiawan, Yanuar Ady , Fynan, Douglas A.

Article Issue Date2025-08 View40
Power distribution bias from equilibrium xenon effects when insufficient neutron histories per cycle are used in Monte Carlo simulation of CANDU6 File

Seo, Yeseul , Hakim, Arief Rahman , Fynan, Douglas A.

Article Issue Date2025-02 View98
Flux Flattening Large Heavy Water Power Reactors with Accelerator-Driven Photoneutron Source File

Hakim, Arief Rahman , Fynan, Douglas A.

Article Issue Date2024-10 View114
Adjustment of long-cycle fast spectrum SMR performance by using gadolinia burnable poison in a moderated outer core driver fuel zone File

Setiawan, Yanuar Ady , Fynan, Douglas A.

Article Issue Date2024-08 View131
Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron Groups in Heavy Water Reactors File

Setiawan, Yanuar Ady , Sengar, Hemantika , Fynan, Douglas A. , Hakim, Arief Rahman

Article Issue Date2023-08 View120
MicroURANUS: Core design for long-cycle lead-bismuth-cooled fast reactor for marine applications File

Nguyen, Tung Dong Cao , Khandaq, Muhammad Farid , Jung, Eun , Choe, Jiwon , Lee, Deokjung , Fynan, Douglas A.

Article Issue Date2021-06 View224
Photoneutron production in heavy water reactor fuel lattice from accelerator-driven bremsstrahlung File

Fynan, Douglas A. , Seo, Yeseul , Kim, Gitae , Barros, Silvia , Kim, Mi Jin

Article Issue Date2021-06 View128
Operator Action-Induced Two-Phase Flow Condition Resulting in Performance Degradation of Interfacing Passive System File

Fynan, Douglas A. , Park, Jinhee

Article Issue Date2021-03 View81
Photoneutron reaction kinematics and error of commonly used approximations File

Fynan, Douglas A.

Article Issue Date2020-10 View120
Optimal working fluid charge and degradation thresholds for a closed-circuit intermediate natural circulation heat transport loop File

Fynan, Douglas A. , Park, Jin Hee

Article Issue Date2018-08 View102
Cooldown procedure success criteria map for the full break size spectrum of SBLOCA File

Fynan, Douglas A. , Cho, Jaehyun , Ahn, Kwang-Il

Article Issue Date2018-01 View105
Pressure drop-flow rate curves for single-phase steam in Combustion Engineering type steam generator U-tubes during severe accidents File

Fynan, Douglas A. , Ahn, Kwang-Il

Article Issue Date2016-12 View145
Implicit Treatment of Technical Specification and Thermal Hydraulic Parameter Uncertainties in Gaussian Process Model to Estimate Safety Margin File File

Fynan, Douglas A. , Ahn, Kwang-Il

Article Issue Date2016-06 View182
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