Materials for Advanced Energy Systems and Fission & Fusion Engineering: Proceedings of the Seventh China-Japan Symposium

[1] T. Kurosu, et al., "Verification Test Program of High Burnup Fuel", Japan-Russia Experts Meeting on Power Reactor Fuels, held in Tokyo, Japan, 19 21 September ( 1994).
[2] H. Hayashi, et al., "Irradiation Characteristics of BWR Step II Lead Use Assemblies", Proc. 1997 ANS Int. Mtg. on LWR Fuel Performance, Portland, Oregon, ( 1997), 296
[3] H. Sakurai, et al., "Irradiation Characteristics of High Burnup BWR Fuels", Proc. 2000 ANS Int. Topical Mtg. on LWR Fuel Performance, Park City, Utah, ( 2001), 151
[4] Y. Mishima, et al., "Proving Test on Reliability for BWR Fuel Assemblies", J. At. Energy Soc. Japan, 29, ( 1987), 90
[5] M. Oishi, et al., "High Burnup Fuel Behavior Studies in NUPEC", IAEA Mtg. on Fuel Performance at High Burnup for Water Reactors, held in Studsvik, Sweden, 5 8 June ( 1990).
[6] S. Koizumi, et al., "Study on Fission Gas Release from High Burnup Fuel", IAEA Mtg. on Fuel Performance at High Burnup for Water Reactors, held in Studsvik, Sweden, 5 8 June ( 1990).
[7] K. Nogita and K. Une, "Formation of Pellet-Cladding Bonding Layer in High Burnup BWR Fuels", J. Nucl. Sci. and Tech., 34 ( 1997) 679.
[8] H. Ohara, et al., "Fuel Behavior During Power Ramp Tests", Proc. 1994 Int. Topical Mtg. on LWR Fuel Performance, West Palm Beach, Fl, ( 1994).
[9] D. Schrire., et al., "Testing Cladding Integrity at High Burnup", IAEA Tec.