Radiation damage concerns for extended light water reactor service

JOM

Volumn 61, Issue 7, 2009, Pages 29-34

  Allen, T R ^a,b   Busby, J T ^c  

^a IDAHO NATIONAL LABORATORY   (United States)

^b UNIVERSITY OF WISCONSIN MADISON   (United States)

^c OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

DIMENSIONAL CHANGES; IRRADIATION DAMAGE; LIGHT WATER; MATERIALS PERFORMANCE; RADIATION-INDUCED SEGREGATION;

IRRADIATION; LIGHT WATER REACTORS; NUCLEAR PROPULSION; NUCLEAR REACTORS; RADIATION DAMAGE;

RADIATION HARDENING;

EID: 70349754499     PISSN: 10474838     EISSN: 15431851     Source Type: Journal    
DOI: 10.1007/s11837-009-0099-2     Document Type: Review

References (22)

1. NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Summary, Vol. 1 (Washington, D.C.: U.S. Nuclear Regulatory Commission, 2001).
2. K. Asano et al., "Changes in Grain Boundary Composition Induced by Neutron Irradiation on Austenitic Stainless Steels," Proc. Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. D. Cubicciotti, E.P. Simonen, and R.E. Gold (LaGrange, IL: American Nuclear Society, 1992), p. 838.
3. A. Jacobs, "Effects of Low Temperature Annealing on the Microstructure and Grain Boundary Chemistry of Irradiated Type 304SS and Correlations with IASCC Resistance," Proc. Seventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (Houston, TX: NACE International, 1995), p. 1021.
4. A.J. Jacobs et al., "The Correlation of Grain Boundary Composition in Irradiated Stainless Steel with IASCC Resistance," Proc. Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. R.E. Gold and E.P. Simonen (Warrendale, PA: TMS, 1993), p. 597.
5. E.A. Kenik, J. Nucl. Mater., 187 (1992), p. 239.
6. S. Nakahigashi et al., J. Nucl. Mater., 179-181 (1992), p 1061.
7. A.J. Jacobs et al., "Influence of Grain Boundary Composition on the IASCC Susceptibility of Type 348 Stainless Steel," Proc. Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. D. Cubicciotti (Houston, TX: National Association of Corrosion Engineers, 1990), pp. 14-21.
8. J. Walmsley et al., "Microchemical Characterization of Grain Boundaries in Irradiated Steels," Proc. Seventh International Symposium on Environment Degradation of Materials in Nuclear Power System-Water Reactors (Houston, TX: NACE International, 1997), p. 985.
9. S.M. Bruemmer et al., J. Nucl. Mater., 274 (1999), pp. 299-314.
10. G.S. Was et al., J. Nucl. Mater., 300 (2002), p. 198.
11. P.J. Maziasz, J. Nucl. Mater., 169 (1989), p. 95.
12. E.H. Lee, P.J. Maziasz, and A.F. Rowcliffe, Phase Stability During Irradiation, ed. J.R. Holland, L.K. Mansur, and D.I. Porter (Warrendale, PA: TMS-AIME, 1981), p. 191.
13. P.J. Maziasz and C.J. McHargue, Internat. Matls. Rev., 32 (1987), p. 190.
14. P.J. Maziasz, J. Nucl. Mater., 205 (1993), p. 118.
15. P.J. Maziasz, MiCon 86: Optimization of Processing, Properties and Service Performance Through Microstructural Control, ASTM-STP-979 (Philadelphia, PA: Am. Soc. For Testing and Matls., 1988), p. 116.
16. S.J. Zinkle, P.J. Maziasz, and R.E. Stoller, J. Nucl. Mater., 206 (1993), p. 266.
17. T.R. Allen et al., J. Nucl. Mater., 255 (1998), pp. 44-58.
18. Julie Tucker et al., "Ab Initio Defect Properties for Modeling Radiation-Induced Segregation in Fe-Ni-Cr Alloys," 13th Environmental Degradation of Materials In Nuclear Power Systems 2007, ed. T.R. Allen, J.T. Busby, and P.J. King (Toronto, ON, Canada: Canadian Nuclear Society, 2007).
19. NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Tabulation of Results, Vol. 2 (Washington, D.C.: U.S. Nuclear Regulatory Commission, 2001).
20. R.D. Leggett and L.C. Walters, J. Nucl. Mater., 204 (1993), p. 23.
21. D.J. Edwards et al., "Influence of Irradiation Temperature and Dose Gradients on the Microstructural Evolution in Neutron-irradiated 316SS," J. Nucl. Materials, 317 (2003), pp. 32-45.
22. J.T. Busby, M.C. Hash, and G.S. Was, "The Relationship Between Hardness and Yield Stress in Irradiated Austenitic and Ferritic Steels," J. Nucl. Mater., 336(2-3) (2005), pp. 267-278.