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Journal of Nuclear Science and Technology Volume 43, 2006 - Issue 5
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ORIGINAL PAPER

Moderator Analysis of Wolsong Units 2/3/4 for the 35% Reactor Inlet Header Break with a Loss of Emergency Core Cooling Injection

Churl YOON Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon, 305-353, Korea
,
Bo Wook RHEE Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon, 305-353, Korea
,
Hyoung Tae KIM Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon, 305-353, Korea
,
Joo Hwan PARK Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon, 305-353, Korea
&
Byung-Joo MIN Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yuseong-gu, Daejeon, 305-353, Korea
Pages 505-513 | Received 05 Aug 2005, Accepted 03 Feb 2006, Published online: 05 Jan 2012

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JadavC. Mandal & ChandrakantR. Sonawane. (2014) Simulation of Moderator Flow and Temperature Inside Calandria of CANDU Reactor Using Artificial Compressibility Method. Heat Transfer Engineering 35:14-15, pages 1254-1266.
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Churl Yoon & Joo Hwan Park. (2007) Simulation of the Internal Flows of an Inlet Diffuser Assembly for the CANDU-6 Moderator Analysis. Nuclear Technology 160:3, pages 314-324.
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Articles from other publishers (13)

Rashid Ali, Zain-Ul-Abdin Alias Faraz, Adam Noora, Muhammad Mudassir Fareed & Shahid Hussain Siyal. (2018) Computational analysis of PT/CT contact behavior for a heavy water reactor at high temperature and pressure. Computational analysis of PT/CT contact behavior for a heavy water reactor at high temperature and pressure.
Eshita Pal, Mukesh Kumar, Arun K. Nayak & Jyeshtharaj B. Joshi. (2016) Experimental and CFD simulations of fluid flow and temperature distribution in a natural circulation driven Passive Moderator Cooling System of an advanced nuclear reactor. Chemical Engineering Science 155, pages 45-64.
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Su Ryong Choi, Jae Jun Jeong, Jae Ryong Lee, Han Young Yoon & Hyoung Tae Kim. (2015) Numerical investigation of the CANDU moderator thermal-hydraulics using the CUPID code. Progress in Nuclear Energy 85, pages 541-547.
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Eshita Pal, Mukesh Kumar, Jyeshtharaj B. Joshi, Arun K. Nayak & Pallippattu K. Vijayan. (2015) CFD simulations of moderator flow inside Calandria of the Passive Moderator Cooling System of an advanced reactor. Nuclear Engineering and Design 292, pages 193-203.
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Su Ryong Choi, Jae Ryong Lee, Hyoung Tae Kim, Han Young Yoon & Jae Jun Jeong. (2014) Preliminary Thermal-Hydraulic Analysis of the CANDU Reactor Moderator Tank using the CUPID Code. Journal of Energy Engineering 23:4, pages 95-105.
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Sang Ki Park, Jae Jun Jeong, Jae Ryong Lee, Han Young Yoon & Hyoung Tae Kim. (2014) Assessment of the CUPID code applicability to the thermal-hydraulic analysis of a CANDU moderator system. Progress in Nuclear Energy 75, pages 72-79.
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Araz Sarchami, Nasser Ashgriz & Marc Kwee. (2014) Three dimensional numerical simulation of a full scale CANDU reactor moderator to study temperature fluctuations. Nuclear Engineering and Design 266, pages 148-154.
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Araz Sarchami, Nasser Ashgriz & Marc Kwee. (2013) Temperature fluctuations inside the CANDU reactor Moderator Test Facility (MTF). Annals of Nuclear Energy 60, pages 157-162.
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Jae Ryong Lee, Sang Gi Park, Han Young Yoon, Hyoung Tae Kim & Jae Jun Jeong. (2013) Numerical study for CANDU moderator temperature prediction by using the two-phase flow analysis code, CUPID. Annals of Nuclear Energy 59, pages 139-148.
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Sang Gi Park, Jae Ryong Lee, Han Young Yoon, Hyoung Tae Kim & Jae Jun Jeong. (2012) Preliminary Analysis of the CANDU Moderator Thermal-Hydraulics using the CUPID Code. Journal of Energy Engineering 21:4, pages 419-426.
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Jae Eun Cha, Hwa Lim Choi, Bo Wook Rhee & Hyoung Tae Kim. (2012) Computational Flow Analysis and Preliminary Measurement for the CANDU-6 Moderator Tank Model. Journal of the Korean Society of Visualization 10:3, pages 30-36.
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Jingke She & Jin Jiang. (2012) Potential improvement of CANDU NPP safety margins by shortening the response time of shutdown systems using FPGA based implementation. Nuclear Engineering and Design 244, pages 43-51.
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Glenn D. Harvel, Richard C. Scrannage & Daniel M. Hobbs. (2011) Scoping assessment of design characteristics for an enhanced calandria tube. Nuclear Engineering and Design 241:8, pages 2688-2697.
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