IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL

다국어 초록 (Multilingual Abstract)

High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear energy systems. Thanks to its excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels such as HT-9 are considered for in-core applications of advanced nuclear reactors. The harsh neutron irradiation environments at the reactor core region pose a unique challenge for structural and cladding materials. Microstructural and microchemical changes resulting from displacement damage are anticipated for structural materials after prolonged neutron exposure. Consequently, various irradiation effects on the service performance of in-core materials need to be understood. In this work, the fundamentals of radiation damage and irradiation effects of the HT-9 martensitic steel are reviewed. The objective of this paper is to provide a background introduction of displacement damage, microstructural evolution, and subsequent effects on mechanical properties of the HT-9 martensitic steel under neutron irradiations. Mechanical test results of the irradiated HT-9 steel obtained from previous fast reactor and fusion programs are summarized along with the information of irradiated microstructure. This review can serve as a starting point for additional investigations on the in-core applications of ferritic/martensitic steels in advanced nuclear reactors.

참고문헌 (Reference)

1 Boltax, A., "Void swelling and irradiation creep relationships" 65 : 174-183, 1977

2 Chin, B. A., "Topical Conference on Ferritic Steels for Use in Nuclear Energy Technologies" The Metallurgical Society of AIME 593-, 1984

3 Kalwa, G., "Topical Conference on Ferritic Alloys for Use in Nuclear Energy Technologies" Met Soc. AIME 235-, 1984

4 Hirth, J. P., "Theory of Dislocations, 2nd Ed." Krieger Publishing Company 1992

5 Mansure, L.K., "Theory and experimental background on dimensional changes in irradiated alloys" 216 : 216-1994, 1994

6 Bullough, R., "The temperature dependence of irradiation creep" 65 : 184-191, 1977

7 Paxton, M. M., "The in-reactor creep of selected ferritic, solid solution strengthened, and precipitation hardened alloys" 95 : 185-, 1980

8 Huang, F., "The fracture toughness database of ferritic alloys irradiated to very high neutron exposure" 187 : 278-, 1992

9 Strang, A., "The effects of microstructural stability on the creep properties of high temperature martensitic 12 Cr steels" 1997

10 Maloy, S. A., "The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels" 356 : 62-, 2006

11 Toloczko, M. B., "Stress and temperature dependence of irradiation creep of selected FCC and BCC steels at low swelling" Fusion Materials Program Semiannula Progress 73-, 2002

12 Ghoniem, N. M., "Selection of alloy steel type for fusion power plant applications in the 350-500C range" 1983

13 Woo, C. H., "Recent advances in the understanding of damage production and its consequences on void swelling, irradiation creep and growth" 239 : 7-23, 1996

14 Okamoto, P.R., "Radiation-induced segregation in binary and ternary alloys" 83 : 2-23, 1979

15 Robertson, J. P., "Radiation hardening and deformation behavior of irradiated ferritic-martensitic Cr-steels" Fusion Materials Semi ann. Prog. Report for period ending 179-187, 1997

16 Stiegler, J. O., "Radiation effects in structural materials" 405-454, 1979

17 Heald, P. T., "Preferential Trapping of Interstitials at Dislocations" 31 (31): 551-, 1975

18 Wollenberger, H., "Phase transformation under irradiation" 216 : 63-77, 1994

19 Anderoglu, O., "Phase stability of an HT-9 duct irradiated in FFTF" 430 : 194-204, 2012

20 Greenwood, L. R., "Neutron Interactions and Atomic Recoil Spectra" 216 : 29-44, 1994

21 Wong, K. L., "Molecular dynamics simulations of point defect interactions in Fe–Cr alloys" 367 : 276-281, 2007

22 Hashimoto, N., "Microstructure of Isotopically-tailored Martensitic steel HT9 Irradiated at 400C to 7 dpa in HFIR" 96-101, 1999

23 Dubuisson, P., "Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phenix" 205 : 178-189, 1993

24 Kai, J.J., "Microstructural analysis of neutronirradiated martensitic steels" 230 : 116-123, 1996

25 Sencer, B.H., "Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443°C" 393 (393): 235-241, 2009

26 Klueh, R. L., "Mechanical properties of neutronirradiated nickel-containing martensitic steels: II. Review and analysis of helium-effect studies" 357 : 169-182, 2006

27 Klueh, R. L., "Mechanical properties of neutron-irradiated nickel-containing martensitic steels: I. Experimental study" 357 : 156-168, 2006

28 Maziasz, P. J., "Materials for Nuclear Reactor Core Applications, Vol. 2" British Nuclear Energy Society 61-, 1988

29 Grossbeck, M. L., "Low-temperature irradiation creep of fusion reactor structural materials" 179 : 130-, 1991

30 Gittus, J., "Irradiation effects in crystalline solids" Applied Science Publishers LTD 1978

31 Byun, T. S., "Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF" 432 : 1-8, 2013

32 Toloczko, M. B., "Irradiation creep of various ferritic alloys irradiated at ~400°C in the PFR and FFTF reactors" 258 : 1163-, 1998

33 Grossbeck, M. L., "Irradiation creep in austenitic and ferritic steels irradiated in a tailored neutron spectrum to induce fusion reactor levels of helium" 233 : 148-, 1996

34 Toloczko, M.B., "Irradiation creep and void swelling of two LMR heats of HT9 at ~400°C and 165 dpa" 233 : 289-292, 1996

35 Garner, F.A., "Irradiation creep and swelling of the fusion heats of PCA, HT9 and 9Cr-1Mo irradiated to high neutron fluence" 179 : 577-580, 1991

36 Toloczko, M. B., "Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr- 1Mo to 208 dpa at ~400°C" 212 : 604-, 1994

37 Toloczko, M. B., "Irradiation creep and swelling from 400 to 600°C of the oxide dispersion strengthened ferritic alloy MA957" 329 : 352-, 2004

38 Garner, F. A., "Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors, In Materials Science and Technology – A Comprehensive Treatment" 1994

39 Klueh, R. L., "Irradiation Effects on Tensile Properties of High-Chromium Ferritic/Martensitic Steels" 73-79, 2003

40 Byun, T. S., "Impact properties of irradiated HT9 from the fuel duct of FFTF" 104 : 111-, 2012

41 Masuyama, F., "History of power plants and progress in heat resistant steels" 41 (41): 621-625, 2001

42 Klueh, R.L., "High-Chromium Ferritic and Martensitic Steels for Nuclear Applicaitons" ASTM

43 Maziasz, P.J., "Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR" 141 : 929-937, 1986

44 Klueh, R.L., "Heat treatment effects on impact toughness of 9Cr–1MoVNb and 12Cr–1MoVW steels irradiated to 100 dpa" 253 : 1269-1274, 1998

45 Rowcliffe, A.F., "Fracture toughness and tensile behavior of ferritic–martensitic steels irradiated at low temperatures" 258 : 1275-, 1998

46 Maziasz, P. J., "Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels" 169 : 95-115, 1989

47 James, L. A., "Fatigue-Crack Propagation Behavior of HT- 9 Steel" 149 : 138-142, 1987

48 Grossbeck, M. L., "Fatigue Behavior of Irradiated Helium-Containing Ferritic Steels for Fusion Reactor Applications" 141 : 966-972, 1986

49 Kluek, R.L., "Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors" 50 (50): 287-310, 2005

50 Gelles, D. S., "Effects of neutron irradiation on microstructure in experimental and commercial ferritic alloys, In Ferritic Alloys for Use in Nuclear Energy Technologies" Met. Soc. AIME 559-, 1984

51 Gelles, D. S., "Effects of irradiation on low activation ferritic alloys: a review, In Reduced Activation Materials for Fusion Reactors" Amer. Soc. for Testing and Materials 113-, 1990

52 Gelles, D. S., "Development of Martensitic Steels for High Neutron Damage Applications" 239 : 99-106, 1996

53 Wolfer, W. G., "Correlation of radiation creep theory with experimental evidence" 90 : 175-192, 1980

54 Maloy, S. A., "Core materials development for the fue cycle R&D program" 415 : 302-305, 2011

55 Paxton, M. M., "Comparison of the in-reactor creep of selected ferritic, solid solution strengthened, and precipitation hardened commercial alloys" 80 : 144-, 1979

56 Garner, F. A., "Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure" 276 : 123-, 2000

57 Allen, T. R, "Cladding and duct materials for advanced nuclear recycle reactors" 60 (60): 15-23, 2008

58 Jenkins, M.L., "Characterization of radiation-damage microstructures by TEM" 216 : 124-156, 1994

59 Gilbon, D., "Behavior of different ferritic steels under ion, electron and fast neutron irradiation" 155 : 1268-1273, 1988

60 Robinson, M.T., "Basic physics of radiation damage production" 216 : 1-28, 1994

61 Averback, A.S., "Atomic displacement processes in irradiated metals" 216 : 49-62, 1994

62 Was, G. S., "Assessment of radiationinduced segregation mechanisms in austenitic and ferritic –martensitic alloys" 411 (411): 41-50, 2011

63 Eyre, B. L., "An Electron Microscope Study of Neutron Irradiation Damage in Alpha-iron" 12 (12): 261-, 1965

64 Norgett, M. J., "A proposed method of calculating displacement dose rates" 33 : 50-54, 1975

65 Woo, C. H., "A SIPA-based theory of irradiation creep in the low swelling rate regime" 191 : 1312-, 1992

66 Kai, J.J., "14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation" 175 : 227-236, 1990