Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

PROGRESS IN NUCLEAR FUEL TECHNOLOGY IN KOREA

  • Published : 2009.05.31
Download PDF
⟨ Previous Next ⟩

Abstract

During the last four decades, 16 Pressurized Water Reactors (PWR) and 4 Pressurized Heavy Water Reactors (PHWR) have been constructed and operated in Korea, and nuclear fuel technology has been developed to a self-reliant state. At first, the PWR fuel design and manufacturing technology was acquired through international cooperation with a foreign partner. Then, the PWR fuel R&D by Korea Atomic Energy Research Institute (KAERI) has improved fuel technology to a self-reliant state in terms of fuel elements, which includes a new cladding material, a large-grained $UO_2$ pellet, a high performance spacer grid, a fuel rod performance code, and fuel assembly test facility. The MOX fuel performance analysis code was developed and validated using the in-reactor test data. MOX fuel test rods were fabricated and their irradiation test was completed by an international program. At the same time, the PWR fuel development by Korea Nuclear Fuel (KNF) has produced new fuel assemblies such as PLUS7 and ACE7. During this process, the design and test technology of fuel assemblies was developed to a self-reliant state. The PHWR fuel manufacturing technology was developed and manufacturing facility was set up by KAERI, independently from the foreign technology. Then, the advanced PHWR fuel, CANFLEX(CANDU Flexible Fuelling), was developed, and an irradiation test was completed in a PHWR. The development of the CANFLEX fuel included a new design of fuel rods and bundles.. The nuclear fuel technology in Korea has been steadily developed in many national R&D programs, and this advanced fuel technology is expected to contribute to a worldwide nuclear renaissance that can create solutions to global warming.

Keywords

References

  1. K.W. Song, Y.H. Jeong, K.S. Kim, J.G. Bang, T.H. Chun, H.K. Kim, and K.N. Song, “High Burnup Fuel Technology in Korea,” Nucl. Eng. & Tech., 40, 21 (2008) https://doi.org/10.5516/NET.2008.40.1.021
  2. J.Y. Park, S.J. Yoo, B.K. Choi, and Y.H. Jeong, “Oxide Microstructures of Advanced Zr Alloys Corroded in 360°C Water Loop,” J. Alloys and Compounds, 437, 274 (2007) https://doi.org/10.1016/j.jallcom.2006.07.101
  3. J.Y. Park, B.K. Choi, S.J. Yoo, and Y.H. Jeong, “Corrosion and Oxide Properties of HANA alloys,” J. ASTM Int., 5, 5, Paper ID JAI101129 https://doi.org/10.1520/JAI101129
  4. Y.H. Jeong, K.O. Lee, and H.G. Kim, “Correlation between Microstructure and Corrosion Behavior of Zr-Nb Binary Alloys,” J. Nucl. Mater., 302, 9 (2002) https://doi.org/10.1016/S0022-3115(02)00703-1
  5. J.Y. Park, B.K. Choi, Y.H. Jeong, and Y.H. Jung, “Corrosion Behavior of Zr Alloys with a High Nb Content,” J. Nucl. Mater., 340, 237 (2005) https://doi.org/10.1016/j.jnucmat.2004.12.003
  6. H.G. Kim, J.Y. Park, and Y.H. Jeong, “Phase Boundary of the Zr-rich Region in Commercial Grade Zr-Nb Alloys,” J. Nucl. Mater., 347, 140 (2005) https://doi.org/10.1016/j.jnucmat.2005.08.008
  7. V.F. Urbanic, B.D. Warr, A. Manolescu, C.K. Chow, and M.W. Shanahan, “Oxidation and Deuterium Uptake of Zr- 2.5 Nb Pressure Tube in CANDU-PHW Reactors,” Zirconium in the Nuclear Industry, ASTM STP 1023, p.20 (1989)
  8. V.F. Urbanic, R.W. Gilbert, “Effect of Microstructure on the Corrosion of Zr-2.5%Nb Alloys,” Proc. of IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion on Zirconium Based Alloys in Water Reactor Environments (IWGFPT/34), IAEA, Vienna, Italy, p.262 (1990)
  9. J.H. Kim, M.H. Lee, B. K. Choi, Y.H. Jeong, “Deformation and Thermal Quench Behavior of HANA Cladding in LOCA Condition,” Proc. of 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, Oct. 2-6 (2005)
  10. J.H. Baek, Y.H. Jeong, “Breakaway Phenomenon of Zr- Based Alloys During a High-temperature Oxidation,” J. Nucl. Mater., 372, 152 (2008) https://doi.org/10.1016/j.jnucmat.2007.02.011
  11. H. Assmann and H. Bairiot, “Process and Product Control of Oxide Powder and Pellets for Reactor Fuel Application”, Guidebook on Quality Control of Water Reactor Fuel, Tech. Report Series No. 221, IAEA, Vienna (1983)
  12. J.A. Turnbull, “The Effect of Grain Size on the Swelling and Gas Release Properties of UO2 During Irradiation,” J. Nucl. Mater., 50 , 62 (1974) https://doi.org/10.1016/0022-3115(74)90061-0
  13. Y. Harada, “Sintering Behaviour of Niobia-doped Large Grain UO2 Pellet,” J. Nucl. Mater., 238, 237 (1997) https://doi.org/10.1016/S0022-3115(96)00443-6
  14. K.W. Song, K.S. Kim, K.W. Kang, and Y. H. Jung, “Effect on Nb2O5 and Oxygen Potential on Sintering Behavior of UO2 Fuel Pellets,” J. Korean Nucl. Soc., 31, 335 (1999)
  15. J.B. Ainscough, F. Rigby, and S.C. Osborn, “The Effect of Titania on Grain Growth and Densification of Sintered UO2,” J. Nucl. Mater., 52, 191 (1974) https://doi.org/10.1016/0022-3115(74)90167-6
  16. L. Bourgeois, Ph. Dehaudt, C. Lemaignam, and A. Hamnou, “Factors Governing Microstructure Development of Cr2O3- Doped UO2 during Sintering,” J. Nucl. Mater., 297, 313 (2001) https://doi.org/10.1016/S0022-3115(01)00626-2
  17. B.E. Ingleby and K. Hand, Fission-Product Behavior in Ceramic Oxide Fuel, Advances in Ceramics, vol. 17, I.J. Hastings (eds), p.57, Amer. Ceramic Soc.(1986)
  18. Y. Harada and S. Doi, “Irradiation on Behavior of Large Grain UO2 Fuel Rod by Active Powder,” J. Nucl. Sci. Technol., 35, 411 (1998) https://doi.org/10.3327/jnst.35.411
  19. G.A. Wood and C.P. Perkins, “Advances in Pellet Technology for Improved Performance at High Burnup,” IAEA-TECDOC-1036, IAEA, Vienna, p. 49 (1998)
  20. K.W. Song, K.S. Kim, K.W. Kang, and Y.H. Jung, “Grain Size Control of UO2 Pellets by Adding Heat-treated U3O8 Particles to UO2 Powder,” J. Nucl. Mater., 317, 204 (2003) https://doi.org/10.1016/S0022-3115(03)00080-1
  21. Jae Ho Yang, Kun Woo. Song, Keon Sik Kim, and Youn Ho. Jung, “A Fabrication Technique for a UO2 Pellet Consisting of UO2 Grains and a Continuous W Channel on the Grain Boundary,” J. Nucl. Mater., 353, 202 (2006) https://doi.org/10.1016/j.jnucmat.2006.01.019
  22. C.B. Lee, Y.S. Yang, Y.M. Kim, D.H. Kim, J.G. Bang, and Y.H. Jung, “High Burnup UO2 Fuel Rod Performance Code INFRA,” Proc. of the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, Sep. 19-22, 2004
  23. C.B. Lee and Y.S. Yang, “INFRA Code Results of FUMEX-II,” IAEA CRP Improvement of models used for fuel behavior simulation (FUMEX-II), IAEA, Vienna, Dec. 5-8, 2005
  24. S. Ravel, et al., “Partitoning of Grain Boundary and Matrix Gas Inventories: Results Obtained Using the ADAGIO Facility,” Fission Gas Behavior in Water Reactor Fuels, Cadarache, France, 2002
  25. D. H. Kim et al., “Post-Irradiation Annealing Test of High Burnup UO2 Fuel”, 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, Oct. 2-6, 2005
  26. Averty, X. et. al., “Tensile Tests on Ring Specimens Machined in M5 Cladding Irradiated 6 Cycles,” IRSN 2003/50(2003)
  27. D. O. Hobson et al., “Embrittlement of Zircaloy Clad Fuel Rods by Steam during LOCA Transients,” ORNL-4758(1972)
  28. H.-K. Kim, Y.-H. Lee, and Y.-H. Jung, “Development of High Temperature & Pressure Fuel Rod Fretting Wear Tester,” Transactions of the KSTLE spring meeting, Korea, 2003
  29. T.M. Frick, T.E. Sobek, and J.R. Reavis, "Overview on the Development and Implement of Methodologies to Compute Vibration and Wear of Steam Generator Tubes,"Symposium on Flow Induced Vibration: Vol. 3, Vibration in Heat Exchanger, p. 149 (1984)
  30. Y.-H. Lee and H.-K. Kim, “Effect of Spring Shapes on the Variation of Loading Conditions and the Wear Behaviour of the Nuclear Fuel Rod During Fretting Wear Tests,” Wear, 263, 451 (2007) https://doi.org/10.1016/j.wear.2006.12.071
  31. Y.-H. Lee and H.-K. Kim, “A Study on the Fretting Wear Resistance of a Zirconium Alloy with the Variation of Supporting Spring Properties,” Key engineering materials, 345-346, 1365 (2007) https://doi.org/10.4028/www.scientific.net/KEM.345-346.1365
  32. H.-K. Kim, Y.-H. Lee, and K.-H. Lee, “On the Geometry of the Fuel Rod Supports Concerning a Fretting Wear Failure,” Nucl. Eng. Design, 238, 3321 (2008) https://doi.org/10.1016/j.nucengdes.2008.08.010
  33. H.-S. Kang, K.-H. Yoon, K.-N. Song, and Y.-H. Jung, “Development of the Flow-induced Vibration Loop for a 5x5 Partial Fuel Assembly,” Transactions of the Korean Nuclear Society Autumn Meeting, Oct. 25-26, 2002
  34. K.-H. Lee, K.-H. Yoon, K.-N. Song, and J.-Y. Kim, “Comparative Study on Flow-Induced Vibration of a 5x5 partial Fuel Assembly for Design Verification of the Newly Developed Spacer Grids,” Transactions of the Korean Nuclear Society Spring Meeting, May 25-26, 2006
  35. K.-H. Lee, J.-Y. Kim, K.-H. Yoon, and K.-N. Song, “High Frequency Flow-Induced Vibration of the 5x5 Test Bundle,” Transactions of the Korean Nuclear Society Autumn Meeting, Nov. 2-3, 2006
  36. K.-H. Lee, K.-H. Yoon, J.-Y. Kim, K.-N. Song, and D.-S. Oh, “Orbital Vibratory Motion of a Fuel Rod in a 5 5 Partial Fuel Assembly in a Confined Axial Flow,” ICAPP'07, France, May 15-19, 2007
  37. K.H. Yoon, H.S. Kang, H.K. Kim, K.N. Song, and Y.H. Jung, “Pendulum Type Impact Test on the Partial Spacer Grid under Room and Operation Temperature Conditions,” KNS Spring Conference, 2002 (in Korean)
  38. K.H. Yoon, K.H. Lee, and K.N. Song, “Buckling Behavior as the Configuration of a Grid Assembly under the Lateral Impact Load,” KSME Spring Conference, 2006(in Korean)
  39. K.H. Yoon, W.K In, H.S. Kang, and K.N Song, “Developed Spacer Grid for Future PWR Fuel Assembly Considered Thermal/Hydraulic and Mechanical/Structural Performance,” ICONE-12, 2004
  40. K.N. Song, K.H. Yoon, J.Y. Kim, and K.H. Lee, “Multydisplinary Design of the Spacer Grid Assembly for PWR,” IWMDE2006, Japan, 2006
  41. H.-K. Kim and S.-J. Kim, “Development of Algorithm for Wear Volume Evaluation using Surface Profile Analysis,” J. Kor. Soc. Tribologists and Lubr. Engrs., 17, 33 (2001)
  42. W.K. In, “Numerical Study of Coolant Mixing caused by the Flow Deflectors in a Nuclear Fuel Bundle,” Nuclear Technology, 134, 187 (2001) https://doi.org/10.13182/NT01-1
  43. W.K. In, T.H. Chun, and C.H Shin, “Numerical Computation of Heat Transfer Enhancement of a PWR Rod Bundle with Mixing Vane Spacers,” Nuclear Technology, 161, 69 (2008) https://doi.org/10.13182/NT08-A3914
  44. D.S. Oh, W.K. In, and T.H. Chun, "Structure of Turbulent Flow in Subchannel of Rod Bundle Downstream of Spacer Grid with Hybrid Flow Mixing Device," ICONE-10, 2002
  45. D.S. Oh, S.K. Chang, B.D. Kim, S.Y. Chun, T.H. Chun, “Pressure Drop Test of Hybrid Mixing Vane Spacer Grid,” KAERI/TR-3441/2007, Korea Atomic Energy Research Institute (2007)
  46. C.H. Shin, Y.J. Choo, S.K. Moon, S.Y. Chun, T.H. Chun, "CHF Performance of Hybrid Mixing Vane Grid for a Nuclear Fuel Bundle," Int. LWR Fuel Performance Meeting, San Francisco, 2007
  47. K.-H. Lee, et al., “Vibration Characteristics of the Grid Cage Assembly,” Transactions of the Korean Nuclear Society Autumn meeting, Oct. 27-28, 2005
  48. K.-H. Lee, et al., “Lateral Vibration Characteristic Test of 16 16 PWR Fuel Assembly,” KSME Annual Spring Meeting, June 7-9, 2006 (in Korean)
  49. Han Soo Kim, Chang Yong Joung, Byung Ho Lee, Jae Yong Oh, Yang Hyun Koo, and Peter Heimgartner, “Applicability of CeO2 as a Surrogate for $PuO_{2}$ in a MOX Fuel Development,” J. Nucl. Mater., 98, 378 (2008) https://doi.org/10.1016/j.jnucmat.2008.05.003
  50. Chang Young Joung, Soo Chul Lee, Si Hyung Kim, Han Soo Kim, and Dong-Seong Sohn, “Fabrication Method for UO2 Pellets with Large Grains or a Single Grain by Sintering in Air,” J. Nucl. Mater., 209, 375 (2008) https://doi.org/10.1016/j.jnucmat.2008.01.011
  51. Christian Hellwig, Uwe Kasemeyer, Guido Ledergerber, Byung-Ho Lee, Young-Woo Lee, and Rakesh Chawla, “Interpretation of Experimental Results from Moderate- Power In-pile Testing of a Pu-Er-Zr-oxide Inert Matrix Fuel,” Annals of Nuclear Energy, 287, 30 (2003) https://doi.org/10.1016/S0306-4549(02)00059-2
  52. Yang-Hyun Koo, Byung-Ho Lee, and Dong-Seong Sohn, “COSMOS: A Computer Code to Analyze LWR $UO_{2}$ and MOX Fuel up to High Burnup,” Annals of Nuclear Energy, 47, 26 (1999) https://doi.org/10.1016/S0306-4549(98)00033-4
  53. Yang-Hyun Koo, Byung-Ho Lee, and Dong-Seong Sohn, “Analysis of Fission Gas Release and Gaseous Swelling in $UO_{2}$ Fuel Under the Effect of External Restraint,” J. Nucl. Mater., 86, 280 (2000) https://doi.org/10.1016/S0022-3115(00)00034-9
  54. Yang-Hyun Koo, Byung-Ho Lee, Jin-Sik Cheon, and Dong- Seong Sohn, “Modeling and Parametric Studies of the Effect of Inhomogeneity on Fission Gas Release in LWR MOX Fuel,” Annals of Nuclear Energy, 271, 29 (2002) https://doi.org/10.1016/S0306-4549(01)00035-4
  55. Byung-Ho Lee, Yang-Hyun Koo, Jin-Sik Cheon, Je-Yong Oh, and Dong-Seong Sohn, “A Unified Thermal Conductivity Model for LWR MOX Fuel Considering Its Microstructural Characteristics,” Actinides 2001, Hayama, Japan, 2001
  56. H. Kampf and G. Karsten, 'Effects of different types of void volumes on the radial temperature distribution of fuel pins,' Nucl Tech., 9, 288 (1970)
  57. Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh, and Dong- Seong Sohn, 'Zircaloy-4 Cladding Corrosion Model Covering a Wide Range of PWR Experiences,' J. Nucl. Mater., 127, 378 (2008) https://doi.org/10.1016/j.jnucmat.2008.04.019
  58. Byung-Ho Lee, Yang-Hyun Koo, Jin-Sik Cheon, and Dong-Seong Sohn, “Modeling of Creep Behavior of Zircaloy-4 by Considering Metallurgical Effect,” Annals of Nuclear Energy, 1, 29 (2002) https://doi.org/10.1016/S0306-4549(01)00030-5
  59. Yang-Hyun Koo, Byung-Ho Lee, Jin-Sik Cheon, and Dong-Seong Sohn, “Pore Pressure and Swelling in the Rim Region of LWR High Burnup $UO_{2}$ Fuel,” J. Nucl. Mater., 213, 295 (2001) https://doi.org/10.1016/S0022-3115(01)00535-9
  60. Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh, Jin-Sik Cheon, and Dong-Seong Sohn, “Improvement of Fuel Performance Code COSMOS with Recent In-pile Data for MOX and $UO_{2}$ Fuels,” Nucl. Tech., 53, 157 (2007) https://doi.org/10.13182/NT07-A3801
  61. Wolfgang Wiesenack, Byung-Ho Lee, and Dong-Seong Sohn, “Irradiation Test of MOX Fuel in the Halden Reactor and the Analysis of Measured Data with the Fuel Performance Code COSMOS,” Nuclear Engineering and Technology, 317, 37 (2005)
  62. Byung-Ho Lee, Yang-Hyun Koo, and Dong-Seong Sohn, “Irradiation test of MOX fuel in the Halden reactor up to 50 MWd/kgHM,” KNS Spring Meeting, May, 2007
  63. K.T. Kim, Y.H. Kim, Y.K. Jang, and D.L. Stucker, “PLUS 7 Advanced Fuel Development for the CE 16x16 type Nuclear Power Plants,” 13th Pacific Basin Nuclear Conference, China, Oct., 2002
  64. S.J. King, K.L. Jeon, R.P. Knott, S.Y. Jeon, M.E. Dye, and R. Esteves, “Advanced PWR Fuel Assembly Development Programs in Korea,” 18th KAIF/KNS Annual Conference, Seoul, Korea, Apr. 9-11, 2003
  65. K.L. Jeon, S.Y. Jeon, K.T. Kim, D.H. Kang, D.S. Suh, M. Boone, S.J. King, R.P. Knott, J.L. Norrell, and R. Esteves, “Updated Status of Advanced 16 16 and 17x17 Fuel Assembly Developments in Korea,” 19th KAIF/KNS Annual Conference, Seoul, Korea, Apr. 25-27, 2004
  66. K.T. Kim and J.M. Suh, “Development of an Advanced PWR Fuel for OPR1000s in Korea,” Nuclear Engineering and Design, 238, 2606 (2008) https://doi.org/10.1016/j.nucengdes.2008.05.005
  67. J.I. Kim, J.C. Shin, Y.K. Jang, K.L. Jeon, Y.B. Chun, S.B. Ahn, W.S. Ryu, P.W. Moon, T.K. Choe, “Irradiated Fuel Examination Program in Korea,” The 23rd KAIF/KNS Annual Conference, Seoul, Korea, Apr. 16-18, 2008
  68. K.T. Kim, Y.K. Jang, and J.I. Kim, “In-Reactor Performance of an Advanced PWR Fuel, PLUS7, for OPR1000 in Korea,” J. of Nuclear Science and Technology, 45, 836 (2008) https://doi.org/10.3327/jnst.45.836
  69. Y.K. Jang, K.L. Jeon, K.T. Kim, J.I. Kim, and J.Y. Park, “Irradiation Performances of Korean Advanced Fuels for Nuclear Power Plants,” 16th Pacific Basin Nuclear Conference, Aomori, Japan, Oct. 13-18, 2008
  70. Y.K. Jang, K. L. Jeon, J. I. Kim, Y. H. Kim, and J. Y. Park, “In-Reactor Performance of Advanced Fuel 16ACE7TM, for Kori 2 Nuclear Power Plant,” 2008 Water Reactor Fuel Performance Meeting, Seoul, Korea, Oct. 19-23, 2008
  71. J.I. Kim, J.C. Shin, Y.K. Jang, K.L. Jeon, Y.B. Chun, P.W. Moon, and T.K. Choe, “Irradiated Fuel Examination Program for Advanced PWR Fuels in Korea,” Proceedings of 2008 KAERI/JAEA Joint Seminar on Advanced Irradiation and PIE Technology, Daejeon, Korea, Nov. 5-7, 2008
  72. K.T. Kim, J.H. Choi, J.M. Suh, “Strategy of Advanced PWR Fuel Development in Korea,” Proc. European Nuclear Society, Brussels, Belgium, Sep.16-20, 2007
  73. H.C. Suk , K-S. Sim, B.G. Kim, C. B. Choi, C. H. Chung, A. D. Lane, D. F. Sears, J. H. K. Lau, I. Oldaker, and P. G. Boezar, “CANFLEX as a CANDU Advanced Fuel Bundle,” Proceedings of the 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, p.UI- 1, Beijing, China, Apr., 1997
  74. G.R. Dimmick, W.W. Inch, J.S. Jun, H.C. Suk, G.I. Hadaller, R.A. Fortman, and R.C. Hayes, “Full Scale Water CHF Testing of the CANFLEX Bundle,” Proceedings of the 6th International Conference on CANDU Fuel, Vol. 2, Niagara Falls, Ontario, Canada, Sep. 26-30, 1999
  75. L.K.H. Leung, D.C. Groeneveld, G.R. Dimmick, D.E. Bullock, and W.W. Inch, “Critical Heat Flux and Pressure Drop for a CANFLEX Bundle String Inside an Axially Non-Uniform Flow Channel,” Proceedings of the 6th International Conference on CANDU Fuel, Vol. 1, Niagara Falls, Ontario, Canada, Sep. 26-30, 1999
  76. L.K.H. Leung, J.S. Jun, G.R. Dimmick, D.E. Bullock, W.W. Inch, and H.C. Suk, “Dryout Power of a CANFLEX Bundle String with Raised Bearing,” Proceedings of the 7th International Conference on CANDU Fuel, Vol. 1, p.27, Kingston, Ontario, Canada, Sep. 23-27, 2001
  77. H.C. Suk, K-S. Sim, B.G. Kim, C.B. Choi, C.H. Chung, A.D. Lane, D.F. Sears, J. H.K. Lau, I. Oldaker, and P.G. Boczar, “CANFLEX as a CANDU Advanced Fuel Bundle,” Proceedings of the 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, p.U1-1, Beijing, China, Apr., 1997
  78. A.D. Lane, G.R. Dimmick, J.H. K. Lau, H.C. Suk, C.H. Chung, and C.B. Choi, "CANFLEX : A New CANDU Fuel Bundle with Expended Operating Capabilities," Proceeding of the 11th KAIF/KNS Annual Conference, Seoul, Korea, Apr. 11-12, 1996
  79. Wayne W.R. Inch, Paul D. Thompson, Patrick J. Reid, and Ho Chun Suk, “Demonstration Irradiation of CANFLEX in CANDU 6 Power Reactor,” Proceedings of 14th KAIF/KNS Annual Conference, Seoul, Korea, Apr. 18-20, 2001
  80. Z. Bilanovic et. al, “Safety Assessment for the 24 CANFLEX Bundle Demonstration Irradiation at Point Lepreau Generating Station,” AECL Report TTR-636, Vol. 1-9 (1998)
  81. H.S. Lim and H.C. Suk, “Safety Assessment for the CANFLEX-NU Fuel Bundles with respect to the 37-ElJement Fuel Bundles,” KAERI/TR-1431/99, Korea Atomic Energy Research Institute (1999)
  82. Wolsong 2, 3 & 4 Final Safety Analysis Report, Korea Electric Power Corporation (1995)
  83. Atomic Energy of Canada Limited, “600 MWe CANDUPHW Wolsong-l Nuclear Power Plant for the Korea Electric Company - Safety Report,” Vol. 1-2(1980)
  84. H.C. Suk, J.S. Jun, J.Y. Jung, M.S. Cho, C.S. Lee, Y.B. Kim Y.D. Kim, S.D. Yi, and H.B. Seo, “Status of the Demonstration Irradiation of the CANDU New Fuel Bundle CANFLEX-NU in Korea,” International CNS CANDU Fuel Conference, Muskoka, Canada, Sep. 22-24, 2003