소듐냉각고속로 원형로 소듐-물 반응 압력완화계통의 배출배관 설계요건 연구

박선희; 한지웅; Sun Hee Park; Ji-Woong Han

Korean Chemical Engineering Research, Vol.56, No.3, 388-403, June, 2018

DOI10.9713/kcer.2018.56.3.388 Export Citation

소듐냉각고속로 원형로 소듐-물 반응 압력완화계통의 배출배관 설계요건 연구

Investigation on Design Requirements of Vent Lines for Sodium-Water Reaction Pressure Relief System of Prototype Generation-IV Sodium-Cooled Fast Reactor

박선희^†, 한지웅

한국원자력연구원 SFR계통설계부, 34057 대전광역시 유성구 대덕대로 989번길 111

Sun Hee Park^†, and Ji-Woong Han

SFR System Design Division, Korea Atomic Energy Research Institute, 111 Daedeok-daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Korea

E-mail:

초록

본 연구는 소듐냉각고속로 원형로 소듐-물 반응 압력완화계통의 소듐, 물, 가스 배출배관 설계에 필요한 요건 도출을 목적으로 한다. 증기발생기의 전열관 파단에 의한 대규모 물 누출 사고 발생 시, 증기발생기 전열관 측의 물과 전열관 외측의 소듐 및 반응생성물을 물배출조와 소듐배출조로 신속하게 배출하기 위해 증기발생기의 소듐 배출배관 파열판 면적, 소듐배출조의 가스 방출배관 직경, 물배출조의 기체 방출배관 직경, 증기발생기의 물 배출배관 직경 등을 설정하기 위한 계산을 수행하였다. 이를 바탕으로 대규모 물 누출 사고 발생 시 증기발생기 내 유체 배출 소요시간 및 압력거동 해석을 수행하였고, 증기발생기 물 배출배관 격리밸브의 차단 설정압력 등의 설계인자를 도출하였다. 본 연구에서 도출된 설계인자들은 소듐냉각고속로 원형로 소듐-물 반응 압력완화계통 설계에 기초자료로 활용할 예정이다.

We investigated design requirements of vent lines for Sodium-Water Reaction Pressure Relief System of Prototype Generation-IV Sodium-Cooled Fast Reactor. We developed design requirements of areas of the rupture disks of the steam generator, a diameter of the gas vent line of the sodium dump tank, a diameter of the gas vent line of the water dump tank, a diameter of the water dump line of the steam generator. With the design requirements, we calculated the time to vent fluid inside the steam generator and analyzed the transient pressure behavior, also evaluated the close pressure value of the isolation valve of the water dump line. Our results are expected to be used as basis information to design Sodium-Water Reaction Pressure Relief System of Prototype Generation IV Sodium-Cooled Fast Reactor.

Keywords:Sodium-cooled Fast Reactor;Sodium-Water Reaction;Pressure Relief System

[References]

Tim A, Sue I, Energy Policy, 36(11), 4323 (2008)
Ahn SJ, Ha KS, Chang WP, Kang SH, Lee KL, Choi CW, Lee SW, Yoo J, Jeong JH, Jeong T, Nucl. Eng. Technol., 48(4), 952 (2016)
Park SH, Min JH, Lee TH, Wi MH, Korean Chem. Eng. Res., 54(6), 863 (2016)
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Shepherd CB, Lapple CE, Ind. Eng. Chem., 32(9), 1246 (1940)
Han GB, Jang JH, Choi C, Lee TJ, Korean J. Chem. Eng., 33(4), 1305 (2016)

[Referenced By]

[1] Tim A, Sue I, Energy Policy, 36(11), 4323 (2008)

[2] Ahn SJ, Ha KS, Chang WP, Kang SH, Lee KL, Choi CW, Lee SW, Yoo J, Jeong JH, Jeong T, Nucl. Eng. Technol., 48(4), 952 (2016)

[3] Park SH, Min JH, Lee TH, Wi MH, Korean Chem. Eng. Res., 54(6), 863 (2016)

[4] Park SH, Ye HY, Lee TH, Korean Chem. Eng. Res., 55(2), 170 (2017)

[5] Shin YW, Wiedermann AH, Eichler TV, Youngdahl CK, Ockert CE, Nucl. Eng. Des., 106(2), 221 (1988)

[6] Ye HY, Choi SR, Han JW, Lee TH, Operation and Safety, October, Gyeongju, Korea(2016).

[7] Takata T, Yamaguchi A, Fukuzawa K, Matsubara K, Nucl. Sci. Eng., 150(2), 221 (2005)

[8] Takata T, Yamaguchi A, Ohshima H, Watanabe A, J. Nucl. Sci. Technol., 43(5), 514 (2006)

[9] Takata T, Yamaguchi A, Uchibori A, Ohshima H, J. Nucl. Sci. Technol., 46(6), 613 (2009)

[10] Shin YW, Chung HH, Wiedermann AH, Tanabe H, 12th International Conference on Structural Mechanics in Reactor Technology, August, Stuttgart, Germany(1993).

[11] Eoh JH, Jeong JY, Kim SO, Hahn D, Nucl. Technol., 152(3), 286 (2005)

[12] Hori M, Atomic Energy Review, 18(3), 707 (1980)

[13] Raj B, Chellapandi P, Rao PRV, Sodium Fast Reactors with Closed Fuel Cycle, 1st ed., CRC Press, Boca Raton, FL(2015).

[14] Idelchik IE, 3rd ed., Begell House, NY(1996). a: Diagram 8-3, p. 518; b: Diagram 4-9, p. 216; c: Diagram 4-1, p. 208; d: Diagram 6-1, p. 357; e: Diagram 6-7, p. 366; f: Diagram 6-7, p. 366; g: Diagram 6-8, p. 367; h: Diagram 4-11, p. 219.

[15] Shepherd CB, Lapple CE, Ind. Eng. Chem., 32(9), 1246 (1940)

[16] Han GB, Jang JH, Choi C, Lee TJ, Korean J. Chem. Eng., 33(4), 1305 (2016)