Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea |
Yoo, Jaewoon
(Korea Atomic Energy Research Institute)
Chang, Jinwook (Korea Atomic Energy Research Institute) Lim, Jae-Yong (Korea Atomic Energy Research Institute) Cheon, Jin-Sik (Korea Atomic Energy Research Institute) Lee, Tae-Ho (Korea Atomic Energy Research Institute) Kim, Sung Kyun (Korea Atomic Energy Research Institute) Lee, Kwi Lim (Korea Atomic Energy Research Institute) Joo, Hyung-Kook (Korea Atomic Energy Research Institute) |
1 | D. Hahn, Y.-I. Kim, C.B. Lee, S.-O. Kim, J.-H. Lee, Y.-B. Lee, B.-H. Kim, H.-Y. Jeong, Conceptual design of the sodium-cooled fast reactor KALIMER-600, Nucl. Eng. Technol. 39 (2007) 193-206. DOI |
2 | D. Hahn, J.-W. Chang, Y.I. Kim, Y.-B. Lee, Advanced SFR design concepts and R&D activities, Nucl. Eng. Technol. 41 (2009) 427-446. DOI |
3 | J. Yoo, J. Chang, H.-K. Joo, Overall reactor system description of prototype Gen-IV sodium cooled fast reactor, Trans. Am. Nucl. Soc. 114 (2016) 694. |
4 | System Description of Prototype Gen-IV Sodium-cooled Fast Reactor, SFR-000-SP-403-001, Korea Atomic Energy Research Institute, 2015. |
5 | Preliminary Safety Information Document of PGSFR, Korea Atomic Energy Research Institute, 2015. |
6 | T. Sofu, A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents, Nucl. Eng. Technol. 47 (2015) 227-239. DOI |
7 | W.R. Robinson, T.H. Bauer, A.E. Wright, E.A. Rhodes, G.S. Stanford, A.E. Klickman, First TREAT transient overpower tests on U-Pu-Zr Fuel: M5 and M6, Trans. Am. Nucl. Soc. 55 (1987) 418. |
8 | J.D. Gabor, R.T. Purviance, R.W. Aeschlimann, B.W. Spencer, Characterization of IFR metal fuel fragmentation, Trans. Am. Nucl. Soc. 54 (1987) 251. |
9 | J.D. Gabor, R.T. Purviance, R.W. Aeschlimann, B.W. Spencer, Pour stream breakup of molten IFR metal fuel in sodium," ANS Topical Meeting, Safety of Next Generation Power Reactors, Seattle, WA, May 1-5, 1988. |
10 | H.P. Planchon, J.I. Sackett, G.H. Golden, R.H. Sevy, Implications of the EBR-II inherent safety demonstration test, Nucl. Eng. Des. 101 (1987) 75-90. DOI |
11 | S.W. Lee, W.-P. Chang, K.-S. Ha, S.J. Ahn, S.H. Kang, C.-W. Choi, K.L. Lee, J.-H. Jeong, J.S. Kim, T. Jeong, Evaluation on invessel source term in PGSFR (2015 results), Trans. of the KNS spring meeting, Jeju, Korea, May 12-13, 2016. |