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Technical Brief

Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea

[+] Author and Article Information
Y. M. Song

Severe Accident and PHWR Safety Research Division,
Korea Atomic Energy Research Institute (KAERI),
989-111, Daedeok-daero, Yuseong-gu,
Daejeon 305-353, South Korea
e-mail: ymsong@kaeri.re.kr

D. H. Kim, S. Y. Park, J. H. Song

Severe Accident and PHWR Safety Research Division,
Korea Atomic Energy Research Institute (KAERI),
989-111, Daedeok-daero, Yuseong-gu,
Daejeon 305-353, South Korea

1Corresponding author.

Manuscript received July 4, 2016; final manuscript received December 23, 2016; published online March 1, 2017. Assoc. Editor: Thambiayah Nitheanandan.

ASME J of Nuclear Rad Sci 3(2), 024501 (Mar 01, 2017) (7 pages) Paper No: NERS-16-1063; doi: 10.1115/1.4035690 History: Received July 04, 2016; Revised December 23, 2016

In Korea, pressurized heavy water-cooled reactors (PHWR) account for 17% of operating units and have taken an important role in providing national energy supply. The recent biggest issue in domestic PHWR community was the continued operation of the Wolsong-1 CANada Deuterium Uranium (CANDU) plant, which has recently been approved to operate for 10 more years after a 30 year design life. In relation to this issue, various actions from both post-Fukushima lessons and Wolsong-1 (WS1) stress test results are being taken. In KAERI R&D, the following topics are studied to support the basis for these actions. First, PHWR severe accident issues such as (1) primary heat transport system (PHTS) overpressure protection capability, (2) containment overpressure protection capability, and (3) bypass source term are evaluated. Second, a computer tool (called MAAP–ISAAC) has been modified and updated to support analyzing Wolsong severe accident issues. Third, a decision supporting tool, called Severe Accident Management Expert (SAMEX)–CANDU, has been developed to aid emergency response experts under severe accident conditions.

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References

Fauske and Associates LLC, 2005, “ MAAP4 Modular Accident Analysis Program for LWR Power Plants User's Manual,” EPRI, Burr Ridge, IL, Project No. RP3131-02.
Gauntt, R. O. , and Cole, R. K. , 2005, “ MELCOR Computer Code Manuals Version 1.8.6,” USNRC, Washington, DC, Report No. NUREG/CR-6119.
Park, S. Y. , Kim, D. H. , and Song, Y. M. , 2008, “ Theory Manual for ISAAC Computer Code,” Korea Atomic Energy Research Institute, Daejeon, South Korea, Report No. KAERI/TR-3648/2008.
Jin, Y. H. , Kim, S. D. , and Park, S. Y. , 2006, “ Severe Accident Management Guidance for Pressurized Heavy Water Reactors,” Korea Atomic Energy Research Institute, Daejeon, South Korea, Report No. KAERI/TR-3284/2006.
Jin, Y. H. , Park, S. Y. , and Song, Y. M. , 2009, “ Application of Severe Accident Management Guidance in the Management of an SGTR Accident at the Wolsong Plants,” Nucl. Eng. Technol., 41(1), pp. 63–70. [CrossRef]
KEPCO, 1995, “ Wolsong Nuclear Power Plant Units No. 2/3/4 Final Safety Analysis Report,” Report No. WSNPP-1.
Chung, C.-H. , Cho, K. T. , Chang, S. W. , and Chung, H. J. , 1996, “ Evaluation of the Ultimate Pressure Capacity of the CANDU-6 Containment Using Material-Nonlinear Model,” J. Korean Soc. Civ. Eng., 16(I-2), pp. 205–216.
Hahm, D. , Choi, I.-K. , and Lee, H.-P. , 2010, “ Assessment of the Internal Pressure Fragility of the CANDU Type Containment Building Using Nonlinear Finite Element Analysis,” J. Comput. Struct. Eng. Inst. Korea, 23(5), pp. 445–452.
KHNP, 2013, “ Wolsong 1 Operating Manual for Containment Filtered Vent System,” Korea Hydro and Nuclear Power Co., Seoul, South Korea, No. 87-73160-7057-001-DM-A.
Song, Y. M. , Jeong, H. S. , Park, S. Y. , Kim, D. H. , and Song, J. H. , 2013, “ Overview of Containment Filtered Vent Under Severe Accident Conditions at Wolsong NPP Unit 1,” Nucl. Eng. Technol., 45(1), pp. 597–604. [CrossRef]
Nitheanandan, T. , and Brown, M. J. , 2013, “ Backup and Ultimate Heat Sinks in CANDU Reactors for Prolonged SBO Accidents,” Nucl. Eng. Technol., 45(5), pp. 589–596. [CrossRef]
KAERI, 2008, “ ISAAC Computer Code User's Manual,” KAERI, Daejeon, South Korea, Report No. KAERI/TR-3645/2008.
KHNP, 2010, “ Probabilistic Safety Assessment and Risk Monitoring System Development for Wolsong Unit 1 (Part 1: Probabilistic Safety Assessment for Wolsong Unit 1),” Rev. 2, Korea Hydro and Nuclear Power Co., Seoul, South Korea.

Figures

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Fig. 1

Core disassembly inside a vessel

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Fig. 2

Degasser condenser tank relief valve

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Fig. 3

Vertical cutaway view of containment

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Fig. 4

Fragility curve for airlock dual seal failure

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Fig. 7

ISAAC development history

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Fig. 8

Decision supporting aid for SAM

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Fig. 9

PSAIS illustration

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