Scaled-Down Moderator Circulation Test Facility at Korea Atomic Energy Research Institute von Kim, Hyoung Tae, Rhee, Bo Wook

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Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400 von Park, Rae-Joon, Ha, Kwang-Soon, Rhee, Bo-Wook, Kim, Hwan Yeol

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Advanced PHWR Safety Technology: PHWR Challenging Issues for Safe Operation and Long-Term Sustainability von Song, Jin Ho, Shen, Wei, Griffiths, Malcolm, Rhee, Bo Wook, Song, YongMann, Naitoh, Masanori

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Benchmark Calculations of a Radiation Heat Transfer for a CANDU Fuel Channel Analysis using the CFD Code von KIM, Hyoung Tae, RHEE, Bo Wook, PARK, Joo Hwan

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Benchmark Calculations of a Radiation Heat Transfer for a CANDU Fuel Channel Analysis using the CFD Code von KIM, Hyoung Tae, RHEE, Bo Wook, PARK, Joo Hwan

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CANDU Safety R&D Status, Challenges, and Prospects in Canada von Shen, Wei, Doyle, F.

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The Effects of the Treatment of the Periodic Boundary Condition in TRIAINA Codes with a Pressure Tube Creep Problem von Jung, Jong Yoeb, Chung, B. Y., Yoo, Seung Yeol, Ryu, Eun Hyun

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Application of a Zircaloy/Steam Oxidation Model to a CFD Code and its Validation against a CANDU Fuel Channel Experiment: CS28-2 von KIM, Hyoung Tae, RHEE, Bo Wook, PARK, Joo Hwan

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PIV measurements of the flow patterns in a CANDU-6 model von Im, Sunghyuk, Kim, Hyoung Tae, Rhee, Bo Wook, Sung, Hyung Jin

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Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code von Kim, Tae Woon, Song, Jinho, Huong, Vo Thi, Kim, Dong Ha, Rhee, Bo Wook, Revankar, Shripad

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The isothermal-fluidic field of a secondary moderator jet in a ¼ scale CANDU-6 reactor model von Kim, Hyoung Tae, Rhee, Bo Wook, Im, Sunghyuk, Sung, Hyung Jin, Atkins, Michael D., Rossouw, Dillon J., Kim, Tongbeum

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A Review of the Scaling Study of the CANDU-6 Moderator Circulation Test Facility von Rhee, Bo Wook, Kim, Hyoung Tae

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Coupled neutronics/thermal–hydraulics analysis of CANDU–SCWR fuel channel von Shan, Jianqiang, Chen, Wei, Rhee, Bo Wook, Leung, Laurence K.H.

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A blind simulation of RD-14M small-break LOCA experiments using CATHENA code von Kim, Hyoung Tae, Rhee, Bo Wook, Park, Joo Hwan

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PIV Measurement of Velocity Distribution in the Moderator Circulation Test (MCT) von Kim, Hyoung Tae, Rhee, Bo Wook, Choi, Hwa-Lim

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Application of a Zircaloy/Steam Oxidation Model to a CFD Code and its Validation against a CANDU Fuel Channel Experiment: CS28-2 von KIM, Hyoung Tae, RHEE, Bo Wook, PARK, Joo Hwan

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CFX simulation of a horizontal heater rods test von Kim, Hyoung Tae, Rhee, Bo Wook, Park, Joo Hwan

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Development and validation of a CATHENA fuel channel model for a post-blowdown analysis of the high temperature thermal–chemical experiment CS28-1 von Rhee, Bo Wook, Kim, Hyoung Tae, Park, Joo Hwan

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Application of the finite volume method to the radial conduction model of the CATHENA code von Kim, Hyoung Tae, Rhee, Bo Wook, Park, Joo Hwan

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Moderator Analysis of Wolsong Units 2/3/4 for the 35% Reactor Inlet Header Break with a Loss of Emergency Core Cooling Injection von YOON, Churl, RHEE, Bo Wook, KIM, Hyoung Tae, PARK, Joo Hwan, MIN, Byung-Joo

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