Out-of-pile and in-pile perfomance of advanded zirconium alloys (HANA) for high burn-up fuel

Journal of Nuclear Science and Technology

Volumn 43, Issue 9, 2006, Pages 977-983

  Jeong, Yong Hwan ^a   Park, Sang Yun ^a   Lee, Myung Ho ^a   Choi, Byung Kwon ^a   Baek, Jong Hyuk ^a   Park, Jeong Yong ^a   Kim, Jun Hwan ^a   Kim, Hyun Gil ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Corrosion; Creep; Fuel cladding; Loss of coolant accident; Microstructure; Neutron irradiation; Zirconium

Indexed keywords

COMPUTER SIMULATION; CORROSION RESISTANCE; CREEP; MICROSTRUCTURE; NEUTRON IRRADIATION; NUCLEAR FUEL CLADDING; NUCLEAR FUELS; PRESSURIZED WATER REACTORS; THICKNESS MEASUREMENT;

COOLANT ACCIDENT LOSSES; CREEP RESISTANCE; FUEL CLADDING; OXIDATION RATE;

ZIRCONIUM ALLOYS;

EID: 33750388101     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2006.9711185     Document Type: Article

References (14)

1. Y. H. Jeong, H. G. Kim, D. J. Kim, et al., “Influence of Nb concentration in the a-matrix on the corrosion behavior of Zr-xNb binary alloys,” J. Nucl. Mater., 323, 72 (2003).
2. H. G. Kim, Y. H. Jeong, T. H. Kim, “Effect of β phase, precipitate and Nb-concentration in matrix on corrosion and oxide characteristics of Zr-xNb alloys,” J. Nucl. Mater., 317, 1 (2003).
3. Y. H. Jeong, K. O. Lee, H. G. Kim, “Correlation between microstructure and corrosion behavior of Zr-Nb binary alloys,” J. Nucl. Mater., 302, 9 (2002).
4. J. Y. Park, B. K. Choi, Y. H. Jeong, et al., “Corrosion behavior of Zr alloys with a high Nb content,” J. Nucl. Mater., 340, 237 (2005).
5. H. G. Kim, J. Y. Park, Y. H. Jeong, “Phase boundary of the Zr-rich region in commercial grade Zr-Nb alloys,” J. Nucl. Mater., 347, 140 (2005).
6. J. Y. Park, B. K. Choi, Y. H. Jeong, et al., “Out-of-pile corrosion properties of HANA alloys,” Proc. 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, Oct. 2-6, 2005, p. 188 (2005).
7. V. F. Urbanic, B. D. Warr, A. Manolescu, et al., “Oxidation and deuterium uptake of Zr-2.5Nb pressure tube in CANDU-PHW reactors,” Zirconium in the Nuclear Industry, ASTM STP 1023, 20 (1989).
8. V. F. Urbanic, R. W. Gilbert, “Effect of microstructure on the corrosion of Zr-2.5%Nb alloys,” Proc. IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion on Zirconium Based Alloys in Water Reactor Environments, International Atomic Energy Agency, Vienna, Italy, IWGFPT/34, p. 262 (1990).
9. J. H. Kim, M. H. Lee, B. K. Choi, et al., “Deformation and thermal quench behavior of HANA cladding in LOCA condition,” Proc. 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, Oct. 2-6, 2005, p. 178 (2005).
10. J. H. Kim, M. H. Lee, B. K. Choi, et al., “Deformation of Zir-caloy-4 cladding during a LOCA transient up to 1200°C,” Nucl. Eng. Des., 234, 157 (2004).
11. J. H. Kim, M. H. Lee, B. K. Choi, et al., Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Nuclear Regulatory Commission 10 CFR 50.46 (1973).
12. J. H. Kim, Y. H. Jeong, “Failure Analysis of Zirconium Cladding under LOCA Situation,” Fuel Safety Research Meeting 2006, Tokai, Japan, April 20-21, 2006, (2006).
13. J. H. Baek, K. B. Park, Y. H. Jeong, “Nb effects on oxidation behavior of Zr-xNb in LOCA temperature range,” Proc. 2004 Int. Mtg. on LWR Fuel Performance, Orlando, Florida, USA, Sep. 19-22, 2004, p. 615 (2004).
14. Y. H. Lee, H. K. Kim, Y. H. Jung, “Experimental study of the alloying elements on the sliding wear behavior of zirconium alloys,” Proc. 2004 Int. Mtg. on LWR Fuel Performance, Orlando, Florida, USA, Sep. 19-22, 2004, p. 83 (2004).