1 |
Toloczko, M. B., D. S. Gelles, F. A. Garner, R. J. Kurtz, K. Abe, "Irradiation creep and swelling from 400 to of the oxide dispersion strengthened ferritic alloy MA957", J. Nucl. Mater. 329-333 (2004) 352.
DOI
ScienceOn
|
2 |
Grossbeck, M. L., L. T. Gibson, S. Jitsukawa, "Irradiation creep in austenitic and ferritic steels irradiated in a tailored neutron spectrum to induce fusion reactor levels of helium"J. Nucl. Mater. 233-237 (1996) 148.
DOI
ScienceOn
|
3 |
James, L. A., "Fatigue-Crack Propagation Behavior of HT-9 Steel," J. Nucl. Mater., 149(1987):138-142.
DOI
ScienceOn
|
4 |
Grossbeck, M. L., Vitek, J. M., and Liu, K. C., "Fatigue Behavior of Irradiated Helium-Containing Ferritic Steels for Fusion Reactor Applications" J. Nucl. Mater., Vol. 141-143, 1986, pp. 966-972.
DOI
ScienceOn
|
5 |
Byun, T. S., W. Ds. Lewis, M. B. Toloczko, S. A. Maloy, "Impact properties of irradiated HT9 from the fuel duct of FFTF," J. Nucl. Mater., 421(2012):104:111.
DOI
ScienceOn
|
6 |
Huang, F. and M. L. Hamilton, "The fracture toughness database of ferritic alloys irradiated to very high neutron exposure", J. Nucl. Mater. 187 (1992) 278
DOI
ScienceOn
|
7 |
Byun, T. S., M. B. Toloczko, T. A. Saleh, S. A. Maloy, "Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF," J. Nucl. Mater., 432(2013): 1-8.
DOI
ScienceOn
|
8 |
Klueh, R.L., N. Hashimoto, M.A., Sokolov, K. Shiba, S. Jitsukawa, "Mechanical properties of neutron-irradiated nickel-containing martensitic steels: I. Experimental study", 357 (2006) 156-168.
DOI
ScienceOn
|
9 |
Klueh, R.L., N. Hashimoto, M.A., Sokolov, P.J. Maziasz, K. Shiba, S. Jitsukawa, "Mechanical properties of neutron-irradiated nickel-containing martensitic steels: II. Review and analysis of helium-effect studies", J. Nucl. Mater, 357 (2006) 169-182.
DOI
ScienceOn
|
10 |
Rowcliffe, A.F., J.P. Robertson, R.L. Klueh, K. Shiba, D. J. Alexander, M. L. Grossbeck and S. Jitsukawa, "Fracture toughness and tensile behavior of ferritic-martensitic steels irradiated at low temperatures", J. Nucl. Mater. 258-263 (1998) 1275.
DOI
ScienceOn
|
11 |
Maloy, S.A., M. B. Tolocako, K.J. McClellan, T. Romero, Y. Kohno, F.A. Garner, R.J. Kurtz and A. Kimura, "The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels", J. Nucl. Mater. 356 (2006) 62.
DOI
ScienceOn
|
12 |
Klueh, R. L., "Irradiation Effects on Tensile Properties of High-Chromium Ferritic/Martensitic Steels," DOE/ER-0313/35 - Vol. 35, Semiannual Progress Report, Dec. 31, 2003, pp.73-79.
|
13 |
Robertson, J.P., R.L. Klueh, K. Shiba and A.F. Rowcliffe, "Radiation hardening and deformation behavior of irradiated ferritic-martensitic Cr-steels", in Fusion Materials Semi ann. Prog. Report for period ending Dec. 31 1997, DOE/ER-0313/23, Oak Ridge National Lab, 1997, pp. 179-187.
|
14 |
Maloy, S. A., M. Toloczko, J. Cole, T. S. Byun, "Core materials development for the fue cycle R&D program," J. Nucl. Mater. 415 (2011) 302-305.
DOI
ScienceOn
|
15 |
Woo, C. H., B.N. Singh, and A.A. Semenov, "Recent advances in the understanding of damage production and its consequences on void swelling, irradiation creep and growth," J. Nucl. Mater., 239 (1996): 7-23.
DOI
ScienceOn
|
16 |
Bullough, R., and M.R. Hayns, "The temperature dependence of irradiation creep," J. Nucl. Mater., 65 (1977): 184-191
DOI
ScienceOn
|
17 |
Wolfer, W. G., "Correlation of radiation creep theory with experimental evidence," J. Nucl. Mater., 90 (1980): 175-192
DOI
ScienceOn
|
18 |
Woo, C. H., and F.A. Garner, "A SIPA-based theory of irradiation creep in the low swelling rate regime," J. Nucl. Mater., 191-194 (1992): 1309-1312.
DOI
ScienceOn
|
19 |
Boltax, A., J.P. Foster, R.A. Weiner, A. Biancheria, "Void swelling and irradiation creep relationships," J. Nucl. Mater., 65(1977): 174-183
DOI
ScienceOn
|
20 |
Garner, F. A., "Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors," Materials Science and Technology - A Comprehensive Treatment, Ed. R.W. Cahn, P. Haasen, E. J. Kramer, 1994.
|
21 |
Paxton, M. M., B. A. Chin, E. R. Gilbert, R. E. Nygren, "Comparison of the in-reactor creep of selected ferritic, solid solution strengthened, and precipitation hardened commercial alloys", J. Nucl. Mater. 80 (1979) 144.
DOI
ScienceOn
|
22 |
Paxton, M. M., B. A. Chin, E. R. Gilbert, "The in-reactor creep of selected ferritic, solid solution strengthened, and precipitation hardened alloys", J. Nucl. Mater. 95 (1980) 185.
DOI
ScienceOn
|
23 |
Chin, B. A., in Topical Conference on Ferritic Steels for Use in Nuclear Energy Technologies, Eds. J. W. Davis, D. J. Michel (The Metallurgical Society of AIME, Warrendale, PA, 1984) 593.
|
24 |
Toloczko, M. B., F. A. Garner, "Stress and temperature dependence of irradiation creep of selected FCC and BCC steels at low swelling" Fusion Materials Program Semiannula Progress Report, (2002) p. 73.
|
25 |
Wong, K. L., J. H. Shim, and B. D. Wirth, "Molecular dynamics simulations of point defect interactions in Fe-Cr alloys," Journal of nuclear materials 367 (2007): 276-281.
|
26 |
Wollenberger, H., "Phase transformation under irradiation", J. Nucl. Mater., 216 (1994) pp. 63-77
DOI
ScienceOn
|
27 |
Okamoto, P.R. and L.E. Rehn, "Radiation-induced segregation in binary and ternary alloys", J. Nucl. Mater., 83 (1979) pp.2-23
DOI
ScienceOn
|
28 |
Was, G. S., J. P. Wharry, B. Frisbie, B. D. Wirth, D. Morgan, J. D. Tucker, and T. R. Allen, "Assessment of radiationinduced segregation mechanisms in austenitic and ferritic-martensitic alloys," Journal of Nuclear Materials 411, no. 1 (2011): 41-50.
DOI
ScienceOn
|
29 |
Maziasz, P.J., "Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels", J. Nulc. Mater., 169 (1989) pp.95-115
DOI
ScienceOn
|
30 |
Klueh, R.L. and D.R. Harries, "High-Chromium Ferritic and Martensitic Steels for Nuclear Applicaitons", ASTM, West Conshohocken, PA.
|
31 |
Maziasz, P.J., R.L. Klueh and J.M. Vitek, "Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR", J. Nucl. Mater., 141-143 (1986) pp. 929-937
DOI
ScienceOn
|
32 |
Anderoglu, O., J. Van den Bosch, P. Hosemann, E. Stergar, B. H. Sencer, D. Bhattacharyya, R. Dickerson, P. Dickerson, M. Hartl, and S. A. Maloy, "Phase stability of an HT-9 duct irradiated in FFTF," Journal of Nuclear Materials, 430 (2012): 194-204.
DOI
ScienceOn
|
33 |
Gelles, D. S., L. E. Thomas, "Effects of neutron irradiation on microstructure in experimental and commercial ferritic alloys," Ferritic Alloys for Use in Nuclear Energy Technologies, Eds, J. W. Davis, and D. J. Michel, Met. Soc. AIME, 1984, 559.
|
34 |
Maziasz, P. J., Materials for Nuclear Reactor Core Applications, Vol. 2, British Nuclear Energy Society, 1988, 61.
|
35 |
Toloczko, M.B. and F.A. Garner, "Irradiation creep and void swelling of two LMR heats of HT9 at and 165 dpa", J. Nucl. Mater., 233-237 (1996) 289-292.
DOI
ScienceOn
|
36 |
Hirth, J. P. and J. Lothe, Theory of Dislocations, 2nd Ed., Krieger Publishing Company, Malabar, Florida, 1992.
|
37 |
Heald, P. T., "Preferential Trapping of Interstitials at Dislocations," Phil. Mag., 31, 3 (1975) 551.
DOI
ScienceOn
|
38 |
Gittus, J., Irradiation effects in crystalline solids, Applied Science Publishers LTD., London, 1978.
|
39 |
Garner, F. A., M. B. Toloczko, B. H. Sencer, "Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure", J. Nucl. Mater. 276 (2000) 123.
DOI
ScienceOn
|
40 |
Toloczko, M. B., F. A. Garner, C. R. Eiholzer, "Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at " J. Nucl. Mater. 212-215 (1994) 604.
DOI
ScienceOn
|
41 |
Toloczko, M. B., F. A. Garner, C. R. Eiholzer, "Irradiation creep of various ferritic alloys irradiated at in the PFR and FFTF reactors" J. Nucl. Mater. 258-263 (1998) 1163.
DOI
ScienceOn
|
42 |
Dubuisson, P., D. Gilbon and J. L. Seran, "Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phenix", J. Nucl. Mater., 205 (1993) 178-189
DOI
ScienceOn
|
43 |
Kluek, R.L., "Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors", International Materials reviews, Vol. 50, No.5, 2005, pp287- 310.
DOI
ScienceOn
|
44 |
Stiegler, J. O. and L.K. Mansur, Ann. Rev. Mater. Sci., "Radiation effects in structural materials", 1979. 9. pp.405-454
|
45 |
Masuyama, F., "History of power plants and progress in heat resistant steels," ISIJ internaltional, 41.6 (2001): 621-625.
|
46 |
Gelles, D. S., "Effects of irradiation on low activation ferritic alloys: a review," Reduced Activation Materials for Fusion Reactors, R. L. Klueh, D. S. Gelles, M. Okada, and N. H. Packin, Eds., Amer. Soc. for Testing and Materials, Philadelphia (1990): 113.
|
47 |
Grossbeck, M. L., L. K. Mansur, "Low-temperature irradiation creep of fusion reactor structural materials" J. Nucl. Mater. 179-181 (1991): 130.
DOI
ScienceOn
|
48 |
Strang, A., and V. Vodarek, "The effects of microstructural stability on the creep properties of high temperature martensitic 12 Cr steels," 7th International Conference on Creep and Fracture of Engineering Materials and Structures, 1997.
|
49 |
Robinson, M.T., "Basic physics of radiation damage production", J. Nucl. Mater., 216(1994): 1-28.
DOI
ScienceOn
|
50 |
Greenwood, L. R., "Neutron Interactions and Atomic Recoil Spectra," J. Nucl. Mater., 216 (1994): 29-44
DOI
ScienceOn
|
51 |
Averback, A.S., "Atomic displacement processes in irradiated metals", J. Nucl. Mater., 216(1994): 49-62
DOI
ScienceOn
|
52 |
Norgett, M.J., M.T. Robinson and I.M. Torrens, "A proposed method of calculating displacement dose rates", Nuclear Engineering and Design, 33 (1975) pp. 50-54
DOI
ScienceOn
|
53 |
Mansure, L.K., "Theory and experimental background on dimensional changes in irradiated alloys", 216 (1994): 97-123.
DOI
ScienceOn
|
54 |
Jenkins, M.L., "Characterization of radiation-damage microstructures by TEM", J. Nucl. Mater., 216 (1994):124-156
DOI
ScienceOn
|
55 |
Eyre, B. L., A. F. Bartlett, "An Electron Microscope Study of Neutron Irradiation Damage in Alpha-iron," Phil. Mag., 12,116 (1965):261
DOI
ScienceOn
|
56 |
Kai, J.J. and G.L. Kulcinshi, "14 MeV nickel-ion irradiated HT-9 ferritic steel with and without helium pre-implantation", J. Nucl. Mater., 175 (1990) pp. 227-236
DOI
ScienceOn
|
57 |
Hashimoto, N., J. P. Robertson, and K. Shiba, "Microstructure of Isotopically-tailored Martensitic steel HT9 Irradiated at 400C to 7 dpa in HFIR," DOE/ER-0313/26 - Vol. 26, Semiannual Progress Report, June 30, 1999, pp.96-101.
|
58 |
Kai, J.J. and R.L. Klueh, "Microstructural analysis of neutronirradiated martensitic steels", J. Nucl. Mater., 230(1996) pp. 116-123
DOI
ScienceOn
|
59 |
Sencer, B.H., J.R. Kennedy, J.I. Cole, S.A. Maloy, F.A. Garner, "Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at ," J. of Nucl. Mater., 393(2) (2009): 235-241.
DOI
ScienceOn
|
60 |
Kalwa, G., K. Haarmann, and J.K. Janssen, in: Topical Conference on Ferritic Alloys for Use in Nuclear Energy Technologies, Eds. J.W Davis and D.J. Michel (Met Soc. AIME, Warrendale, PA, 1984) 235.
|
61 |
Klueh, R.L. and D.J. Alexander, "Heat treatment effects on impact toughness of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated to 100 dpa", J. Nucl. Mater., 253-258(1998) 1269-1274.
|
62 |
Gelles, D. S., "Development of Martensitic Steels for High Neutron Damage Applications," J. Nucl. Mater., 239 (1996): 99-106.
DOI
ScienceOn
|
63 |
Ghoniem, N. M., J. Blink, and N. Hoffman, "Selection of alloy steel type for fusion power plant applications in the 350-500C range," Proc. of the Topical Conf. on Ferritic Alloys for Use in Nuclear Technology, Snowbird, Utah. 1983.
|
64 |
Gilbon, D. and C. Rivera, "Behavior of different ferritic steels under ion, electron and fast neutron irradiation", J. Nucl. Mater., 155-157 (1988) pp.1268-1273
DOI
ScienceOn
|
65 |
Garner, F.A. and R.J. Puigh, "Irradiation creep and swelling of the fusion heats of PCA, HT9 and 9Cr-1Mo irradiated to high neutron fluence", J. Nucl. Mater., 179-181 (1991) 577-580.
DOI
ScienceOn
|
66 |
Allen, T. R, J. T. Busby, R. L. Klueh, S. A. Maloy, and M. B. Toloczko, "Cladding and duct materials for advanced nuclear recycle reactors," JOM 60, no. 1 (2008): 15-23.
DOI
|