-
1
-
-
50349085649
-
-
Glob. Nucl. Energy Partnersh. Tech. Integ. Off. 2007. Global Nuclear Energy Partnership technology development plan. GNEP-TECH-TR-PP-2007-00020, rev. 0, Idaho Natl. Lab., Idaho Falls, ID
-
Glob. Nucl. Energy Partnersh. Tech. Integ. Off. 2007. Global Nuclear Energy Partnership technology development plan. GNEP-TECH-TR-PP-2007-00020, rev. 0, Idaho Natl. Lab., Idaho Falls, ID
-
-
-
-
2
-
-
50349095966
-
-
U.S. DOE Nucl. Energy Res. Advis. Comm./Generation IV Int. Forum GIF. 2002. A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF-002-00. OECD Nucl. Energy Agency, Le Seine Saint-Germain, 12, boulevard Îles, F-92130 Issy-les-Moulineaux, Fr.
-
U.S. DOE Nucl. Energy Res. Advis. Comm./Generation IV Int. Forum GIF. 2002. A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF-002-00. OECD Nucl. Energy Agency, Le Seine Saint-Germain, 12, boulevard Îles, F-92130 Issy-les-Moulineaux, Fr.
-
-
-
-
4
-
-
3342977325
-
A plan for the development of fusion energy
-
Goldston R, Abdou M, Baker C, Campbell M, Chan V, et al. 2002. A plan for the development of fusion energy. J. Fus. Energy 21:61-111
-
(2002)
J. Fus. Energy
, vol.21
, pp. 61-111
-
-
Goldston, R.1
Abdou, M.2
Baker, C.3
Campbell, M.4
Chan, V.5
-
5
-
-
0346969543
-
The development of structural materials for fusion reactors
-
Ehrlich K. 1999. The development of structural materials for fusion reactors. Philos. Trans. R. Soc. London Ser. A 357:595-623
-
(1999)
Philos. Trans. R. Soc. London Ser. A
, vol.357
, pp. 595-623
-
-
Ehrlich, K.1
-
6
-
-
0034316858
-
Operating temperature windows for fusion reactor structural materials
-
Zinkle SJ, Ghoniem NM, 2000. Operating temperature windows for fusion reactor structural materials. Fus. Eng. Des. 51-52:55-71
-
(2000)
Fus. Eng. Des
, vol.51-52
, pp. 55-71
-
-
Zinkle, S.J.1
Ghoniem, N.M.2
-
7
-
-
3342895062
-
Materials for the plasma-facing components of fusion reactors
-
Bolt H, Barabash V, Krauss W, Linke J, Neu R, et al. 2004. Materials for the plasma-facing components of fusion reactors. J. Nucl. Mater. 329-333:66-73
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 66-73
-
-
Bolt, H.1
Barabash, V.2
Krauss, W.3
Linke, J.4
Neu, R.5
-
8
-
-
27844479222
-
Advanced materials for fusion technology
-
Zinkle SJ. 2005. Advanced materials for fusion technology. Fus. Eng. Des. 74:31-40
-
(2005)
Fus. Eng. Des
, vol.74
, pp. 31-40
-
-
Zinkle, S.J.1
-
9
-
-
20944431905
-
Fusion materials science: Overview of challenges and recent progress
-
Zinkle SJ. 2005. Fusion materials science: overview of challenges and recent progress. Phys. Plasmas 12:058101
-
(2005)
Phys. Plasmas
, vol.12
, pp. 058101
-
-
Zinkle, S.J.1
-
10
-
-
50349084707
-
-
Corwin WR. 2006. U.S. Generation IV reactor integrated materials technology program. Nucl. Eng. Technol. 38:1-28
-
Corwin WR. 2006. U.S. Generation IV reactor integrated materials technology program. Nucl. Eng. Technol. 38:1-28
-
-
-
-
11
-
-
34447575717
-
Critical questions in materials science and engineering for successful development of fusion power
-
Bloom EE, Busby JT, Duty CE, Maziasz PJ, McGreevy TE, et al. 2007. Critical questions in materials science and engineering for successful development of fusion power. J. Nucl. Mater. 367-370:1-10
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 1-10
-
-
Bloom, E.E.1
Busby, J.T.2
Duty, C.E.3
Maziasz, P.J.4
McGreevy, T.E.5
-
12
-
-
46949108158
-
Cladding and duct materials for advanced nuclear recycle reactors
-
Allen TR, BusbyJT, Klueh RL, Maloy SA, Toloczko MB. 2008. Cladding and duct materials for advanced nuclear recycle reactors. JOA 60:15-23
-
(2008)
JOA
, vol.60
, pp. 15-23
-
-
Allen, T.R.1
Busby, J.T.2
Klueh, R.L.3
Maloy, S.A.4
Toloczko, M.B.5
-
13
-
-
34447535267
-
Materials degradation in fission reactors: Lessons learned of relevance to fusion reactor systems
-
Was GS. 2007. Materials degradation in fission reactors: lessons learned of relevance to fusion reactor systems. J. Nucl. Mater. 367-370:11-20
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 11-20
-
-
Was, G.S.1
-
14
-
-
50349085869
-
-
Olander DR. 1976. Fundamental aspects of nuclear reactor fuel elements. OSTI ID: 7343826:TID-26711-P1
-
Olander DR. 1976. Fundamental aspects of nuclear reactor fuel elements. OSTI ID: 7343826:TID-26711-P1
-
-
-
-
16
-
-
0003259505
-
Mechanisms and kinetics of radiation effects in metals and alloys
-
ed. GR Freeman, pp, New York: Wiley-Intersci
-
Mansur LK. 1987. Mechanisms and kinetics of radiation effects in metals and alloys. In Kinetics of Nonhomogenous Processes, ed. GR Freeman, pp. 377-463. New York: Wiley-Intersci.
-
(1987)
Kinetics of Nonhomogenous Processes
, pp. 377-463
-
-
Mansur, L.K.1
-
17
-
-
0020283580
-
-
Stoller RE, Odette GR. 1982. The effect of matrix cavities and cavity density on die formation of precipitate associated voids and swelling in multiphase stainless steels. Proc. Int. Symp. Eff. Irradiat. Mater., 11th, Scottsdale, ASTM Spec. Tech. Publ. 782:275-94. Philadelphia: ASTM
-
Stoller RE, Odette GR. 1982. The effect of matrix cavities and cavity density on die formation of precipitate associated voids and swelling in multiphase stainless steels. Proc. Int. Symp. Eff. Irradiat. Mater., 11th, Scottsdale, ASTM Spec. Tech. Publ. 782:275-94. Philadelphia: ASTM
-
-
-
-
18
-
-
85147082187
-
A composite model of microstructural evolution in austenitic stainless steel under fast neutron irradiation
-
ASTM Spec. Tech. Publ, Philadelphia: ASTM
-
Stoller RE, Odette GR. 1987. A composite model of microstructural evolution in austenitic stainless steel under fast neutron irradiation. Int. Symp. lnflu. Irradiat. Mater. Prop., 13th, Seattle, ASTM Spec. Tech. Publ. 955:371-92. Philadelphia: ASTM
-
(1987)
Int. Symp. lnflu. Irradiat. Mater. Prop., 13th, Seattle
, vol.955
, pp. 371-392
-
-
Stoller, R.E.1
Odette, G.R.2
-
19
-
-
49149132938
-
Fission fusion correlations for swelling and microstructure in stainless steels: The effect of the helium to displacement per atom ratio
-
Odette GR, Mazaisz PJ, Spitzbagel JA. 1982. Fission fusion correlations for swelling and microstructure in stainless steels: the effect of the helium to displacement per atom ratio. J. Nucl. Mater. 103:1289-303
-
(1982)
J. Nucl. Mater
, vol.103
, pp. 1289-1303
-
-
Odette, G.R.1
Mazaisz, P.J.2
Spitzbagel, J.A.3
-
20
-
-
33947669072
-
A creep fracture model for irradiated and helium injected austenitic stainless steel
-
Vagarali SS, Odette GR. 1981. A creep fracture model for irradiated and helium injected austenitic stainless steel. J. Nucl. Mater. 103:1239-43
-
(1981)
J. Nucl. Mater
, vol.103
, pp. 1239-1243
-
-
Vagarali, S.S.1
Odette, G.R.2
-
21
-
-
0020795869
-
On the modeling of the high-temperature embrittlement of metals containing helium
-
Trinkaus H. 1983. On the modeling of the high-temperature embrittlement of metals containing helium. J. Nucl. Mater. 118:39-49
-
(1983)
J. Nucl. Mater
, vol.118
, pp. 39-49
-
-
Trinkaus, H.1
-
22
-
-
85047199524
-
The influence of helium on the bulk properties of fusion-reactor structural-materials
-
Ullmaier H. 1984. The influence of helium on the bulk properties of fusion-reactor structural-materials. Nucl. Fus. 24:1039-83
-
(1984)
Nucl. Fus
, vol.24
, pp. 1039-1083
-
-
Ullmaier, H.1
-
23
-
-
0020745761
-
A model for in-reactor stress rupture of austenitic stainless-steels
-
Odette GR. 1984. A model for in-reactor stress rupture of austenitic stainless-steels. J. Nucl. Mater. 122:435-41
-
(1984)
J. Nucl. Mater
, vol.122
, pp. 435-441
-
-
Odette, G.R.1
-
24
-
-
0021480508
-
Modeling microstructural evolution in fusion reactor environment
-
Odette GR. 1985. Modeling microstructural evolution in fusion reactor environment. J. Nucl. Mater. 133:127-33
-
(1985)
J. Nucl. Mater
, vol.133
, pp. 127-133
-
-
Odette, G.R.1
-
25
-
-
0022045629
-
Analytical solutions for helium bubble parameters using a hard sphere equation of state
-
Stoller RE, Odette GR. 1985. Analytical solutions for helium bubble parameters using a hard sphere equation of state. J. Nucl. Mater. 131:118-25
-
(1985)
J. Nucl. Mater
, vol.131
, pp. 118-125
-
-
Stoller, R.E.1
Odette, G.R.2
-
26
-
-
0023348302
-
Nucleation of grain-boundary cavities under the combined influence of helium and applied stress
-
Alhajji JN, Ghoniem NM. 1987. Nucleation of grain-boundary cavities under the combined influence of helium and applied stress. Acta Metall. 35:1067-75
-
(1987)
Acta Metall
, vol.35
, pp. 1067-1075
-
-
Alhajji, J.N.1
Ghoniem, N.M.2
-
27
-
-
85167782749
-
A comparison of the relative importance of helium and vacancy accumulation in void nucleation
-
ASTM Spec. Tech. Publ, Philadelphia: ASTM
-
Stoller RE, Odette GR. 1987. A comparison of the relative importance of helium and vacancy accumulation in void nucleation. Int. Symp. Infiu. Irradiat. Mater. Prop., 13th, Seattle, ASTM Spec. Tech. Publ. 955:358-70. Philadelphia: ASTM
-
(1987)
Int. Symp. Infiu. Irradiat. Mater. Prop., 13th, Seattle
, vol.955
, pp. 358-370
-
-
Stoller, R.E.1
Odette, G.R.2
-
28
-
-
0024035483
-
On mechanisms controlling swelling in ferritic and martensitic alloys
-
Odette GR. 1988. On mechanisms controlling swelling in ferritic and martensitic alloys. J. Nucl. Mater. 155-157:921-27
-
(1988)
J. Nucl. Mater
, vol.155-157
, pp. 921-927
-
-
Odette, G.R.1
-
29
-
-
0033890307
-
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high-neutron exposure
-
Garner FA, Toloczko MB, Sencer BH. 2000. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high-neutron exposure. J. Nucl. Mater. 276:123-42
-
(2000)
J. Nucl. Mater
, vol.276
, pp. 123-142
-
-
Garner, F.A.1
Toloczko, M.B.2
Sencer, B.H.3
-
30
-
-
33748274910
-
On the effects of irradiation on the yield stress changes and hardening and non-hardening embrittlement of 8Cr tempered martensitic steels: Compilation and analysis of existing data
-
Yamamoto T, Odette GR, Kishimoto H, Rensman JW, Miao PF. 2006. On the effects of irradiation on the yield stress changes and hardening and non-hardening embrittlement of 8Cr tempered martensitic steels: compilation and analysis of existing data. J. Nucl. Mater. 356:27-49
-
(2006)
J. Nucl. Mater
, vol.356
, pp. 27-49
-
-
Yamamoto, T.1
Odette, G.R.2
Kishimoto, H.3
Rensman, J.W.4
Miao, P.F.5
-
31
-
-
0021558396
-
On the physical basis for the swelling resistance of ferritic steels
-
New York: Metall. Soc. Am. Inst. Min. Metall. Petroleum Eng
-
Sniegowski JJ, Wolfer WG. 1984. On the physical basis for the swelling resistance of ferritic steels. In Proc. Top. Conf. Ferritic Alloys Use Nucl. Energy Technol., pp. 579-86. New York: Metall. Soc. Am. Inst. Min. Metall. Petroleum Eng.
-
(1984)
Proc. Top. Conf. Ferritic Alloys Use Nucl. Energy Technol
, pp. 579-586
-
-
Sniegowski, J.J.1
Wolfer, W.G.2
-
32
-
-
0025429773
-
Mechanisms of swelling suppression in cold-worked phosphorus-modified Fe-Ni-Cr alloys
-
Lee EH, Mansur LK. 1990. Mechanisms of swelling suppression in cold-worked phosphorus-modified Fe-Ni-Cr alloys. Philos. Mag. A 61:733-49
-
(1990)
Philos. Mag. A
, vol.61
, pp. 733-749
-
-
Lee, E.H.1
Mansur, L.K.2
-
33
-
-
0027677314
-
Overview of microstructural evolution in neutron-irradiated austenitic stainless-steels
-
Maziasz PJ. 1993. Overview of microstructural evolution in neutron-irradiated austenitic stainless-steels. J. Nucl. Mater. 205:118-45
-
(1993)
J. Nucl. Mater
, vol.205
, pp. 118-145
-
-
Maziasz, P.J.1
-
34
-
-
1642283439
-
Swelling rate versus swelling correlation in 20% cold-worked 316 stainless steels
-
Ukai S, Uwaba T. 2003. Swelling rate versus swelling correlation in 20% cold-worked 316 stainless steels. J. Nucl. Mater. 317:93-101
-
(2003)
J. Nucl. Mater
, vol.317
, pp. 93-101
-
-
Ukai, S.1
Uwaba, T.2
-
35
-
-
0036937909
-
High resistance to helium embrittlement in reduced activation martensitic steels
-
Kimura A, Kasada R, Morishita K, Sugano R, Hasegawa A, et al. 2002. High resistance to helium embrittlement in reduced activation martensitic steels. J. Nucl. Mater. 307:521-26
-
(2002)
J. Nucl. Mater
, vol.307
, pp. 521-526
-
-
Kimura, A.1
Kasada, R.2
Morishita, K.3
Sugano, R.4
Hasegawa, A.5
-
36
-
-
34547841451
-
Ferritic/martensitic steels for next-generation reactors
-
Klueh RL, Nelson AT. 2007. Ferritic/martensitic steels for next-generation reactors. J. Nucl. Mater. 371:37-52
-
(2007)
J. Nucl. Mater
, vol.371
, pp. 37-52
-
-
Klueh, R.L.1
Nelson, A.T.2
-
37
-
-
34447570654
-
New nano-particle strengthened ferritic/martensitic steels by conventional thermo-mechanical treatment
-
Klueh RL, Hashimoto N, Maziasz PJ. 2007. New nano-particle strengthened ferritic/martensitic steels by conventional thermo-mechanical treatment. J. Nucl. Mater. 367-370:48-53
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 48-53
-
-
Klueh, R.L.1
Hashimoto, N.2
Maziasz, P.J.3
-
38
-
-
0346772452
-
Dispersion strengthened ferritic alloy for use in liquid-metal fast breeder reactors.
-
U.S. Patent No. 4,075,010
-
Fisher JJ. 1978. Dispersion strengthened ferritic alloy for use in liquid-metal fast breeder reactors. U.S. Patent No. 4,075,010
-
(1978)
-
-
Fisher, J.J.1
-
39
-
-
34447521943
-
Pre- and post-deformation microstructures of oxide dispersion strengthened ferritic steels
-
Kasada R, Toda N, Yutani K, Cho HS, Kishimoto H, Kimura A. 2007. Pre- and post-deformation microstructures of oxide dispersion strengthened ferritic steels. J. Nucl. Mater. 367-370:222-28
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 222-228
-
-
Kasada, R.1
Toda, N.2
Yutani, K.3
Cho, H.S.4
Kishimoto, H.5
Kimura, A.6
-
40
-
-
50349099740
-
Fabrication technological development of the oxide dispersion strengthened alloy MA957 for fast reactor applications
-
Richland, WA: Pac. Northwest Lab
-
Hamilton ML, Gelles DS, Lobsinger RJ, Johnson GD, Brown WF, et al. 2000. Fabrication technological development of the oxide dispersion strengthened alloy MA957 for fast reactor applications. PNL-13168, Richland, WA: Pac. Northwest Lab.
-
(2000)
PNL-13168
-
-
Hamilton, M.L.1
Gelles, D.S.2
Lobsinger, R.J.3
Johnson, G.D.4
Brown, W.F.5
-
41
-
-
50349098558
-
Nano-mesoscopic structure control in 9Cr-ODS ferritic steels
-
Ukai S, Ohtsuka S. 2007. Nano-mesoscopic structure control in 9Cr-ODS ferritic steels. Energy Mater. 2:26-35
-
(2007)
Energy Mater
, vol.2
, pp. 26-35
-
-
Ukai, S.1
Ohtsuka, S.2
-
42
-
-
0347891779
-
Processing condition of oxide dispersion strengthened ferritic steel by mechanical alloying
-
Warrendale, PA: TMS
-
Okuda T, Nomura S, Shikakura S, Asabe K, Tanoue S, Fujiwara M. 1990. Processing condition of oxide dispersion strengthened ferritic steel by mechanical alloying. Proc. Symp. Solid State Powder Processing, pp. 195-202. Warrendale, PA: TMS
-
(1990)
Proc. Symp. Solid State Powder Processing
, pp. 195-202
-
-
Okuda, T.1
Nomura, S.2
Shikakura, S.3
Asabe, K.4
Tanoue, S.5
Fujiwara, M.6
-
43
-
-
44949278925
-
Cavity formation by thermal treatment in ODS steel
-
Igata N, Nagato T, Yumoto H. 1991. Cavity formation by thermal treatment in ODS steel. J. Nucl. Mater. 179-181:279-81
-
(1991)
J. Nucl. Mater
, vol.179-181
, pp. 279-281
-
-
Igata, N.1
Nagato, T.2
Yumoto, H.3
-
44
-
-
0027658967
-
Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials
-
Ukai S, Harada M, Okada H, Inoue M, Nomura S, et al. 1993. Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials. J. Nucl. Mater. 204:65-73
-
(1993)
J. Nucl. Mater
, vol.204
, pp. 65-73
-
-
Ukai, S.1
Harada, M.2
Okada, H.3
Inoue, M.4
Nomura, S.5
-
45
-
-
0027878549
-
Tube manufacturing and mechanical properties of oxide dispersion strengthened ferritic steel
-
Ukai S, Harada M, Okada H, Inoue M, Nomura S, et al. 1993. Tube manufacturing and mechanical properties of oxide dispersion strengthened ferritic steel. J. Nucl. Mater. 204:74-80
-
(1993)
J. Nucl. Mater
, vol.204
, pp. 74-80
-
-
Ukai, S.1
Harada, M.2
Okada, H.3
Inoue, M.4
Nomura, S.5
-
46
-
-
0029405876
-
Dispersion behavior of oxide particles in mechanically alloyed ODS steel
-
Okuda T, Fujiwara M. 1995. Dispersion behavior of oxide particles in mechanically alloyed ODS steel. J. Mater. Sci. Lett. 14:1600-3
-
(1995)
J. Mater. Sci. Lett
, vol.14
, pp. 1600-1603
-
-
Okuda, T.1
Fujiwara, M.2
-
47
-
-
0030402344
-
Effects of grain morphology and texture on high temperature deformation in oxide dispersion strengthened ferritic steels
-
Okada H, Ukai S, Inoue M. 1996. Effects of grain morphology and texture on high temperature deformation in oxide dispersion strengthened ferritic steels. J. Nucl. Sci. Technol. 33:936-43
-
(1996)
J. Nucl. Sci. Technol
, vol.33
, pp. 936-943
-
-
Okada, H.1
Ukai, S.2
Inoue, M.3
-
48
-
-
0000043887
-
Development of oxide dispersion strengthened steels for FBR core application. I. Improvement of mechanical properties by recrystallization processing
-
Ukai S, Nishida T, Okada H, Okuda T, Fujiwara M, Asabe K. 1997. Development of oxide dispersion strengthened steels for FBR core application. I. Improvement of mechanical properties by recrystallization processing. J. Nucl. Sci. Technol. 34:256-63
-
(1997)
J. Nucl. Sci. Technol
, vol.34
, pp. 256-263
-
-
Ukai, S.1
Nishida, T.2
Okada, H.3
Okuda, T.4
Fujiwara, M.5
Asabe, K.6
-
49
-
-
0032595380
-
Preliminary tube manufacturing of oxide dispersion strengthened ferritic steels with recrystallized structure
-
Ukai S, Yoshitake T, Mizuta S,Matsudaira Y, Hagi S, Kobayashi T. 1999. Preliminary tube manufacturing of oxide dispersion strengthened ferritic steels with recrystallized structure. J. Nucl. Sci. Technol. 36:710-12
-
(1999)
J. Nucl. Sci. Technol
, vol.36
, pp. 710-712
-
-
Ukai, S.1
Yoshitake, T.2
Mizuta, S.3
Matsudaira, Y.4
Hagi, S.5
Kobayashi, T.6
-
50
-
-
0034546196
-
Tube manufacturing and characterization of oxide dispersion strengthened ferritic steels
-
Ukai S, Mizuta S, Yoshitake T, Okuda T, Fujiwara M, et al. 2000. Tube manufacturing and characterization of oxide dispersion strengthened ferritic steels. J. Nucl. Mater. 283-287:702-6
-
(2000)
J. Nucl. Mater
, vol.283-287
, pp. 702-706
-
-
Ukai, S.1
Mizuta, S.2
Yoshitake, T.3
Okuda, T.4
Fujiwara, M.5
-
51
-
-
0036698994
-
Characterization of high temperature creep properties in recrystallized 12Cr-ODS ferritic steel claddings
-
Ukai S, Okuda T, Fujiwara M, Kobayashi T, Mizuta S, Nakashima H. 2002. Characterization of high temperature creep properties in recrystallized 12Cr-ODS ferritic steel claddings. J. Nucl. Sci. Technol. 39:872-79
-
(2002)
J. Nucl. Sci. Technol
, vol.39
, pp. 872-879
-
-
Ukai, S.1
Okuda, T.2
Fujiwara, M.3
Kobayashi, T.4
Mizuta, S.5
Nakashima, H.6
-
52
-
-
0036942168
-
Perspective of ODS alloys application in nuclear environments
-
Ukai S, Fujiwara M. 2002. Perspective of ODS alloys application in nuclear environments. J. Nucl. Mater. 307-311:749-57
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 749-757
-
-
Ukai, S.1
Fujiwara, M.2
-
53
-
-
8644290820
-
Formation of nanoscale complex oxide particles in mechanically alloyed ferritic steel
-
Yamashita S, Ohtsuka S, Akasaka N, Ukai S, Ohnuki S. 2004. Formation of nanoscale complex oxide particles in mechanically alloyed ferritic steel. Philos. Mag. Lett. 84:525-29
-
(2004)
Philos. Mag. Lett
, vol.84
, pp. 525-529
-
-
Yamashita, S.1
Ohtsuka, S.2
Akasaka, N.3
Ukai, S.4
Ohnuki, S.5
-
54
-
-
70249092957
-
Development of fuel clad materials for high burn-up operation of LWR. J
-
pap. ID JAI12371
-
Cho H, Kimura A, Ukai S, Fujiwara M. 2005. Development of fuel clad materials for high burn-up operation of LWR. J ASTMInt. 2:111-19 (pap. ID JAI12371)
-
(2005)
ASTMInt
, vol.2
, pp. 111-119
-
-
Cho, H.1
Kimura, A.2
Ukai, S.3
Fujiwara, M.4
-
55
-
-
34447542857
-
Embrittlement and hardening during thermal aging of high Cr oxide dispersion strengthened alloys
-
Lee JS, Jang CH, Kim IS, Kimura A. 2007. Embrittlement and hardening during thermal aging of high Cr oxide dispersion strengthened alloys. J. Nucl. Mater. 367:229-33
-
(2007)
J. Nucl. Mater
, vol.367
, pp. 229-233
-
-
Lee, J.S.1
Jang, C.H.2
Kim, I.S.3
Kimura, A.4
-
56
-
-
0032180905
-
R&D of oxide dispersion strengthened ferritic martensitic steels for FBR
-
Ukai S, Nishida T, Okuda T, Yoshitake T. 1998. R&D of oxide dispersion strengthened ferritic martensitic steels for FBR. J. Nucl. Mater. 258-263:1745-49
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 1745-1749
-
-
Ukai, S.1
Nishida, T.2
Okuda, T.3
Yoshitake, T.4
-
57
-
-
0032045790
-
Development of oxide dispersion strengthened steels for FBR core application. II. Morphology improvement by martensite transformation
-
Ukai S, NishidaT, Okuda T, Yoshitake T. 1998. Development of oxide dispersion strengthened steels for FBR core application. II. Morphology improvement by martensite transformation. J. Nucl. Sci. Technol. 35:294-300
-
(1998)
J. Nucl. Sci. Technol
, vol.35
, pp. 294-300
-
-
Ukai, S.1
Nishida, T.2
Okuda, T.3
Yoshitake, T.4
-
58
-
-
0036934680
-
Consolidation process study of 9Cr-ODS martensitic steels
-
Ukai S, Hatakeyama K, Mizuta S, Fujiwara M, Okuda T. 2002. Consolidation process study of 9Cr-ODS martensitic steels. J. Nucl. Mater. 307-311:758-62
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 758-762
-
-
Ukai, S.1
Hatakeyama, K.2
Mizuta, S.3
Fujiwara, M.4
Okuda, T.5
-
59
-
-
0036631159
-
Development of 9Cr-ODS martensitic steel claddings for fuel pins by means of ferrite to austenite phase transition
-
Ukai S, Mizuta S, Fujiwara M, Okuda T, Kobayashi T. 2002. Development of 9Cr-ODS martensitic steel claddings for fuel pins by means of ferrite to austenite phase transition. J. Nucl. Sci. Technol. 39:778-88
-
(2002)
J. Nucl. Sci. Technol
, vol.39
, pp. 778-788
-
-
Ukai, S.1
Mizuta, S.2
Fujiwara, M.3
Okuda, T.4
Kobayashi, T.5
-
60
-
-
3342926314
-
Tube manufacturing trials by different routes in 9CrW-ODS martensitic steels
-
Ukai S, Narita T, Alamo A, Parmentier P. 2004. Tube manufacturing trials by different routes in 9CrW-ODS martensitic steels. J. Nucl. Mater. 329-333:356-61
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 356-361
-
-
Ukai, S.1
Narita, T.2
Alamo, A.3
Parmentier, P.4
-
61
-
-
3342949468
-
Pressurized resistance welding technology development in 9Cr-ODS martensitic steels
-
Seki M, Hirako K, Kono S, Kihara Y, Kaito T, Ukai S. 2004. Pressurized resistance welding technology development in 9Cr-ODS martensitic steels. J. Nucl. Mater. 329-333:1534-38
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 1534-1538
-
-
Seki, M.1
Hirako, K.2
Kono, S.3
Kihara, Y.4
Kaito, T.5
Ukai, S.6
-
62
-
-
13844321638
-
Nano-structure control in ODS martensitic steels by means of selecting titanium and oxygen contents
-
Ohtsuka S, Ukai S, Fujiwara M, Kaito T, Narita T. 2005. Nano-structure control in ODS martensitic steels by means of selecting titanium and oxygen contents. J. Phys. Chem. Solids 66:571-75
-
(2005)
J. Phys. Chem. Solids
, vol.66
, pp. 571-575
-
-
Ohtsuka, S.1
Ukai, S.2
Fujiwara, M.3
Kaito, T.4
Narita, T.5
-
63
-
-
32544443059
-
Microstructural evolution during creep of 9Cr-ODS steels
-
Sakasegawa H, Ohtsuka S, Ukai S, Tanigawa H, Fujiwara M, et al. 2006. Microstructural evolution during creep of 9Cr-ODS steels. Fus. Eng. Des. 81:1013-18
-
(2006)
Fus. Eng. Des
, vol.81
, pp. 1013-1018
-
-
Sakasegawa, H.1
Ohtsuka, S.2
Ukai, S.3
Tanigawa, H.4
Fujiwara, M.5
-
64
-
-
34447515573
-
Properties of friction welds between 9Cr-ODS martensitic and ferritic-martensitic steels
-
Uwaba T, Ukai S, Nakai T, Fujiwara M. 2007. Properties of friction welds between 9Cr-ODS martensitic and ferritic-martensitic steels. J. Nucl. Mater. 367-370:1213-17
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 1213-1217
-
-
Uwaba, T.1
Ukai, S.2
Nakai, T.3
Fujiwara, M.4
-
65
-
-
34447515699
-
Nano-mesoscopic structural control of 9Cr ODS martensitic steel for improving creep strength
-
Ohtsuka S, Ukai S, Sakasegawa H, Fujiwara M, Kaito T, Narita T. 2007. Nano-mesoscopic structural control of 9Cr ODS martensitic steel for improving creep strength. J. Nucl. Mater. 367-370:160-65
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 160-165
-
-
Ohtsuka, S.1
Ukai, S.2
Sakasegawa, H.3
Fujiwara, M.4
Kaito, T.5
Narita, T.6
-
66
-
-
34447561624
-
Low cycle fatigue properties of ODS ferritic-martensitic steels at high-temperature
-
Ukai S, Ohtsuka S. 2007. Low cycle fatigue properties of ODS ferritic-martensitic steels at high-temperature. J. Nucl. Mater. 367-370:234-38
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 234-238
-
-
Ukai, S.1
Ohtsuka, S.2
-
67
-
-
34447557724
-
Particle size effects in mechanically alloyed 9Cr ODS steel powder
-
Sakasegawa H, Ohtsuka S, Ukai S, Tanigawa H, Fujiwara M, et al. 2007. Particle size effects in mechanically alloyed 9Cr ODS steel powder. J. Nucl. Mater. 367-370:185-90
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 185-190
-
-
Sakasegawa, H.1
Ohtsuka, S.2
Ukai, S.3
Tanigawa, H.4
Fujiwara, M.5
-
68
-
-
0346549056
-
Hardness of 12Cr-8Mo ferritic steels irradiated by Ni ions
-
Ohta J, Ohmura T, Kako K, Tokiwai M, Suzuki T. 1995. Hardness of 12Cr-8Mo ferritic steels irradiated by Ni ions. J. Nucl. Mater. 225:187-91
-
(1995)
J. Nucl. Mater
, vol.225
, pp. 187-191
-
-
Ohta, J.1
Ohmura, T.2
Kako, K.3
Tokiwai, M.4
Suzuki, T.5
-
69
-
-
0032180896
-
Void formation and microstructural development in oxide dispersion strengthened ferritic steels during electron irradiation
-
Saito J, Suda T, Yamashita S, Ohnuki S, Takahashi H, et al. 1998. Void formation and microstructural development in oxide dispersion strengthened ferritic steels during electron irradiation. J. Nucl. Mater. 258-263:1264-68
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 1264-1268
-
-
Saito, J.1
Suda, T.2
Yamashita, S.3
Ohnuki, S.4
Takahashi, H.5
-
70
-
-
0032181033
-
Superior Charpy impact properties of ODS ferritic steel irradiated in JOYO
-
Kuwabara T, Kurishita H, Ukai S, Narui M, Mizuta S, et al. 1998. Superior Charpy impact properties of ODS ferritic steel irradiated in JOYO. J. Nucl. Mater. 258-263:1236-41
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 1236-1241
-
-
Kuwabara, T.1
Kurishita, H.2
Ukai, S.3
Narui, M.4
Mizuta, S.5
-
71
-
-
0034547395
-
Effect of mechanical alloying parameters on irradiation damage in oxide dispersion strengthened ferritic steels
-
Yamashita S, Watanabe S, Ohnuki S, Takahashi H, Akasaka N, Ukai S. 2000. Effect of mechanical alloying parameters on irradiation damage in oxide dispersion strengthened ferritic steels. J. Nucl. Mater. 283-287:647-51
-
(2000)
J. Nucl. Mater
, vol.283-287
, pp. 647-651
-
-
Yamashita, S.1
Watanabe, S.2
Ohnuki, S.3
Takahashi, H.4
Akasaka, N.5
Ukai, S.6
-
72
-
-
3342878409
-
Microstructural changes of neutron irradiated ODS ferritic and martensitic steels
-
Akasaka N, Yamashita S, Yoshitake T, Ukai S, Kimura A. 2004. Microstructural changes of neutron irradiated ODS ferritic and martensitic steels. J. Nucl. Mater. 329-333:1053-56
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 1053-1056
-
-
Akasaka, N.1
Yamashita, S.2
Yoshitake, T.3
Ukai, S.4
Kimura, A.5
-
73
-
-
0036935007
-
Phase stability of oxide dispersion strengthened ferritic steels in neutron irradiation
-
Yamashita S, Oka K, Ohnuki S, Akasaka N, Ukai S. 2002. Phase stability of oxide dispersion strengthened ferritic steels in neutron irradiation. J. Nucl. Mater. 307-311:283-88
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 283-288
-
-
Yamashita, S.1
Oka, K.2
Ohnuki, S.3
Akasaka, N.4
Ukai, S.5
-
74
-
-
3342990197
-
Nano-oxide particle stability of 9-12Cr grain morphology modified ODS steels under neutron irradiation
-
Yamashita S, Akasaka N, Ohnuki S. 2004. Nano-oxide particle stability of 9-12Cr grain morphology modified ODS steels under neutron irradiation. J. Nucl. Mater. 329-333:377-81
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 377-381
-
-
Yamashita, S.1
Akasaka, N.2
Ohnuki, S.3
-
75
-
-
3342985096
-
Ring-tensile properties of irradiated oxide dispersion strengthened ferritic/martensitic steel claddings
-
Yoshitake T, Abe Y, Akasaka N, Ohtsuka S, Ukai S, Kimura A. 2004. Ring-tensile properties of irradiated oxide dispersion strengthened ferritic/martensitic steel claddings. J. Nucl. Mater. 329-333:342-46
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 342-346
-
-
Yoshitake, T.1
Abe, Y.2
Akasaka, N.3
Ohtsuka, S.4
Ukai, S.5
Kimura, A.6
-
76
-
-
33144467999
-
-
Yamashita S, Oka K, Yoshitake T, Akasaka N, Ukai S, Ohnuki S. 2004. Oxide particle stability in oxide dispersion strengthened ferritic steels during neutron irradiation. Int. Symp. Eff. Radiat. Mater., 21st, Tucson, ASTM Spec. Top. Publ. 1447:391. Philadelphia: ASTM
-
Yamashita S, Oka K, Yoshitake T, Akasaka N, Ukai S, Ohnuki S. 2004. Oxide particle stability in oxide dispersion strengthened ferritic steels during neutron irradiation. Int. Symp. Eff. Radiat. Mater., 21st, Tucson, ASTM Spec. Top. Publ. 1447:391. Philadelphia: ASTM
-
-
-
-
77
-
-
19644364979
-
Mechanical behavior of oxide dispersion strengthened steels irradiated in JOYO
-
Yamashita S, Yoshitake T, Akasaka N, Ukai S, Kimura A. 2005. Mechanical behavior of oxide dispersion strengthened steels irradiated in JOYO. Mater. Trans. 46:493-97
-
(2005)
Mater. Trans
, vol.46
, pp. 493-497
-
-
Yamashita, S.1
Yoshitake, T.2
Akasaka, N.3
Ukai, S.4
Kimura, A.5
-
78
-
-
32544458209
-
Helium cavity formation research on oxide dispersion strengthening (ODS) ferritic steels utilizing dual-ion irradiation facility
-
Kishimoto H, Yutani K, Kasada R, Kimura A. 2006. Helium cavity formation research on oxide dispersion strengthening (ODS) ferritic steels utilizing dual-ion irradiation facility. Fits. Eng. Der. 81:1045-49
-
(2006)
Fits. Eng. Der
, vol.81
, pp. 1045-1049
-
-
Kishimoto, H.1
Yutani, K.2
Kasada, R.3
Kimura, A.4
-
79
-
-
34447519061
-
Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels
-
Kishimoto H, Yutani K, Kasada R, Hashitomi O, Kimura A. 2007. Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels. J. Nucl. Mater. 367-370:179-84
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 179-184
-
-
Kishimoto, H.1
Yutani, K.2
Kasada, R.3
Hashitomi, O.4
Kimura, A.5
-
80
-
-
34447573693
-
Effects of neutron irradiation on the tensile properties of high-Cr oxide dispersion strengthened ferritic steels
-
Cho HS, Kasada R, Kimura A. 2007. Effects of neutron irradiation on the tensile properties of high-Cr oxide dispersion strengthened ferritic steels. J. Nucl. Mater. 367-370:239-43
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 239-243
-
-
Cho, H.S.1
Kasada, R.2
Kimura, A.3
-
81
-
-
34447579948
-
Microstructural development of a heavily neutronirradiated ODS ferritic steel (MA957) at elevated temperature
-
Yamashita S, Akasaka N, Ukai S, Ohnuki S. 2007. Microstructural development of a heavily neutronirradiated ODS ferritic steel (MA957) at elevated temperature. J. Nucl. Mater. 367-370:202-7
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 202-207
-
-
Yamashita, S.1
Akasaka, N.2
Ukai, S.3
Ohnuki, S.4
-
82
-
-
34447558385
-
Evaluation of helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation
-
Yutani K, Kishimoto H, Kasada R, Kimura A. 2007. Evaluation of helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation. J. Nucl. Mater. 367-370:423-27
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 423-427
-
-
Yutani, K.1
Kishimoto, H.2
Kasada, R.3
Kimura, A.4
-
83
-
-
34247130867
-
High burnup fuel cladding materials R&D for advanced nuclear systems: Nano-sized oxide dispersion strengthening steels
-
Kimura A, Cho HS, Toda N, Kasada R, Utani K, et al. 2007. High burnup fuel cladding materials R&D for advanced nuclear systems: nano-sized oxide dispersion strengthening steels. J. Nucl. Sci. Technol. 44:323-28
-
(2007)
J. Nucl. Sci. Technol
, vol.44
, pp. 323-328
-
-
Kimura, A.1
Cho, H.S.2
Toda, N.3
Kasada, R.4
Utani, K.5
-
84
-
-
0036603238
-
ODS steel clad MOX fuel-pin fabrication and irradiation performance in EBR-II
-
BottcherJ, Ukai S, Inoue M. 2002. ODS steel clad MOX fuel-pin fabrication and irradiation performance in EBR-II. Nucl. Technol. 138:238-45
-
(2002)
Nucl. Technol
, vol.138
, pp. 238-245
-
-
Bottcher, J.1
Ukai, S.2
Inoue, M.3
-
85
-
-
14844347693
-
Oxide dispersion strengthened (ODS) fuel pins for BOR-60 irradiation test
-
Ukai S, Kaito T, Seki M, Mayorshin A Shishalov O. 2005. Oxide dispersion strengthened (ODS) fuel pins for BOR-60 irradiation test. J. Nucl. Sci. Technol. 42:109-22
-
(2005)
J. Nucl. Sci. Technol
, vol.42
, pp. 109-122
-
-
Ukai, S.1
Kaito, T.2
Seki, M.3
Mayorshin, A.4
Shishalov, O.5
-
86
-
-
51249169815
-
Crystallographic texture in mechanically alloyed oxide-dispersion-strengthened MA956 and MA957 steels
-
Chou TS, Bhadeshia HKDH. 1993. Crystallographic texture in mechanically alloyed oxide-dispersion-strengthened MA956 and MA957 steels, Metall. Trans. A 24A:773-79
-
(1993)
Metall. Trans. A
, vol.24 A
, pp. 773-779
-
-
Chou, T.S.1
Bhadeshia, H.K.D.H.2
-
87
-
-
0035537636
-
Manufacturing and microstructural evolution of mechanically alloyed oxide dispersion strengthened superalloys
-
Capdevila C, Bhadeshia HKDH. 2001. Manufacturing and microstructural evolution of mechanically alloyed oxide dispersion strengthened superalloys. Adv. Eng. Mater. 3:647-56
-
(2001)
Adv. Eng. Mater
, vol.3
, pp. 647-656
-
-
Capdevila, C.1
Bhadeshia, H.K.D.H.2
-
88
-
-
0036694670
-
Origin of porosity in oxide-dispersion-strengthened alloys produced by mechanical alloying
-
Chen YL, Jones AR, Miller U. 2002. Origin of porosity in oxide-dispersion-strengthened alloys produced by mechanical alloying. Metall. Mater. Trans. A 33A:2713-18
-
(2002)
Metall. Mater. Trans. A
, vol.33 A
, pp. 2713-2718
-
-
Chen, Y.L.1
Jones, A.R.2
Miller, U.3
-
89
-
-
3342877559
-
Assessment of ODS-14%Cr ferritic alloy for high temperature applications
-
Alamo A, Lambard V, Averty X, Mathon MH. 2004. Assessment of ODS-14%Cr ferritic alloy for high temperature applications. J. Nucl. Mater. 329-333:333-37
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 333-337
-
-
Alamo, A.1
Lambard, V.2
Averty, X.3
Mathon, M.H.4
-
90
-
-
5744231428
-
Deformation and damage processes during creep of Incoloy MA957
-
Wilshire B, Lieu TD. 2004. Deformation and damage processes during creep of Incoloy MA957. Mater. Sci Eng. A386:81-90
-
(2004)
Mater. Sci Eng. A
, vol.386
, pp. 81-90
-
-
Wilshire, B.1
Lieu, T.D.2
-
91
-
-
34447498886
-
Mechanical properties of 9Cr martensitic steels and ODS-FeCr alloys after neutron irradiation at 325°C up to 42 dpa
-
Alamo A, Bertin JL, Shamardin VK, Wident P. 2007. Mechanical properties of 9Cr martensitic steels and ODS-FeCr alloys after neutron irradiation at 325°C up to 42 dpa. J. Nucl. Mater. 367-370:54-59
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 54-59
-
-
Alamo, A.1
Bertin, J.L.2
Shamardin, V.K.3
Wident, P.4
-
92
-
-
0036944549
-
Mechanical and microstructural properties of a hipped RAFM. ODS-steel
-
KlimenkovM
-
Lindau R, Moslang A, Schirra M, Schlossmacher P, KlimenkovM. 2002. Mechanical and microstructural properties of a hipped RAFM. ODS-steel. J. Nucl. Mater. 307-311:769-72
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 769-772
-
-
Lindau, R.1
Moslang, A.2
Schirra, M.3
Schlossmacher, P.4
-
93
-
-
0036938605
-
Microstructure and mechanical properties of two ODS ferritic/martensitic steels
-
Schaeublin R, Leguey T, Spatig P, Baluc N, Victoria M. 2002. Microstructure and mechanical properties of two ODS ferritic/martensitic steels. J. Nucl. Mater. 307-311:778-82
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 778-782
-
-
Schaeublin, R.1
Leguey, T.2
Spatig, P.3
Baluc, N.4
Victoria, M.5
-
94
-
-
0036864713
-
Mechanical tests on two batches of oxide dispersion strengthened RAFM steel (Eurofer97)
-
Lucon E. 2002. Mechanical tests on two batches of oxide dispersion strengthened RAFM steel (Eurofer97). Fus. Eng. Des. 61-62:683-89
-
(2002)
Fus. Eng. Des
, vol.61-62
, pp. 683-689
-
-
Lucon, E.1
-
95
-
-
0037295990
-
HRTEM study of yttrium oxide particles in ODS steels for fusion reactor application
-
Klimiankou M, Lindau R, Moslang A. 2003. HRTEM study of yttrium oxide particles in ODS steels for fusion reactor application. J. Cryst. Growth 249:381-87
-
(2003)
J. Cryst. Growth
, vol.249
, pp. 381-387
-
-
Klimiankou, M.1
Lindau, R.2
Moslang, A.3
-
96
-
-
19444371669
-
4 ODS EUROFER steels during their elaboration by mechanical milling and hot isostatic pressing
-
4 ODS EUROFER steels during their elaboration by mechanical milling and hot isostatic pressing. J. Nucl. Mater. 335:83-102
-
(2004)
J. Nucl. Mater
, vol.335
, pp. 83-102
-
-
Cayron, C.1
Rath, E.2
Chu, I.3
Launois, S.4
-
97
-
-
9544242733
-
Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels
-
Monnet I, Dubuisson P, Serruys Y, Ruault MO, Kaitasov O, Jouffrey B. 2004. Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels. J. Nucl. Mater. 335:311-21
-
(2004)
J. Nucl. Mater
, vol.335
, pp. 311-321
-
-
Monnet, I.1
Dubuisson, P.2
Serruys, Y.3
Ruault, M.O.4
Kaitasov, O.5
Jouffrey, B.6
-
98
-
-
3342893264
-
TEM characterization of structure and composition of nanosized ODS particles in reduced activation ferritic-martensitic steels
-
Klimiankou M, Lindau R, Moslang A. 2004, TEM characterization of structure and composition of nanosized ODS particles in reduced activation ferritic-martensitic steels. J. Nucl. Mater. 329-333:347-51
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 347-351
-
-
Klimiankou, M.1
Lindau, R.2
Moslang, A.3
-
99
-
-
27844465405
-
Present development status of EUROFER and ODS-EUROFER for application in blanket concepts
-
Lindau R, Moslang A, Rieth M, Klimiankou M, Materna-Morris E, et al. 2005. Present development status of EUROFER and ODS-EUROFER for application in blanket concepts. Fus. Eng. Des. 75-79:989-96
-
(2005)
Fus. Eng. Des
, vol.75-79
, pp. 989-996
-
-
Lindau, R.1
Moslang, A.2
Rieth, M.3
Klimiankou, M.4
Materna-Morris, E.5
-
100
-
-
10044273355
-
Energy-filtered TEM imaging and EELS study of ODS particles and argon-filled cavities in ferritic-martensitic steels
-
Klimiankou M, Lindau R, Moslang A, 2005. Energy-filtered TEM imaging and EELS study of ODS particles and argon-filled cavities in ferritic-martensitic steels. Micron 36:1-8
-
(2005)
Micron
, vol.36
, pp. 1-8
-
-
Klimiankou, M.1
Lindau, R.2
Moslang, A.3
-
101
-
-
27844611975
-
Thermal creep behaviour of the Eurofer97 RAFM steel and the two European ODS Eurofer97 steels
-
Yu G, Nita N, Baluc N. 2005, Thermal creep behaviour of the Eurofer97 RAFM steel and the two European ODS Eurofer97 steels. Fus. Eng. Des. 75-79:1037-41
-
(2005)
Fus. Eng. Des
, vol.75-79
, pp. 1037-1041
-
-
Yu, G.1
Nita, N.2
Baluc, N.3
-
102
-
-
30744474721
-
Small angle neutron scattering study of irradiated martensitic steels: Relation between microstructural evolution and hardening
-
Mathon M, Carlan Y, Averty X, Alamo A, Novion CH. 2005. Small angle neutron scattering study of irradiated martensitic steels: relation between microstructural evolution and hardening. J. ASTM Int. 2:120-34
-
(2005)
J. ASTM Int
, vol.2
, pp. 120-134
-
-
Mathon, M.1
Carlan, Y.2
Averty, X.3
Alamo, A.4
Novion, C.H.5
-
104
-
-
38849198577
-
Microstructure and Charpy impact properties of 12-14Cr oxide-dispersion strengthened steels
-
Oksiuta Z, Baluc N, 2008. Microstructure and Charpy impact properties of 12-14Cr oxide-dispersion strengthened steels. J. Nucl. Mater. 374:178-84
-
(2008)
J. Nucl. Mater
, vol.374
, pp. 178-184
-
-
Oksiuta, Z.1
Baluc, N.2
-
105
-
-
17644448349
-
Development of an oxide dispersion strengthened, reduced-activation steel for fusion energy
-
Romanoski GR, Snead LL, Klueh RL, Hoelzer DT. 2000. Development of an oxide dispersion strengthened, reduced-activation steel for fusion energy. J. Nucl. Mater. 283-287:642-46
-
(2000)
J. Nucl. Mater
, vol.283-287
, pp. 642-646
-
-
Romanoski, G.R.1
Snead, L.L.2
Klueh, R.L.3
Hoelzer, D.T.4
-
107
-
-
0036934457
-
Tensile and creep properties of an oxide dispersion-strengthened ferritic steel
-
Klueh RL, Maziasz PJ, Kim IS, Heatherley L, Hoelzer DT, et al. 2002. Tensile and creep properties of an oxide dispersion-strengthened ferritic steel. J. Nucl. Mater. 307-311:773-77
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 773-777
-
-
Klueh, R.L.1
Maziasz, P.J.2
Kim, I.S.3
Heatherley, L.4
Hoelzer, D.T.5
-
108
-
-
0036934425
-
Tensile and fracture toughness properties of MA957: Implications to the development of nanocomposited ferritic alloys
-
Alinger MJ, Odette GR, Lucas GE. 2002. Tensile and fracture toughness properties of MA957: implications to the development of nanocomposited ferritic alloys. J. Nucl. Mater. 307-311:484-89
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 484-489
-
-
Alinger, M.J.1
Odette, G.R.2
Lucas, G.E.3
-
109
-
-
0038454851
-
Atom probe tomography of nanoscale particles in ODS ferritic alloys
-
Miller MK, Kenik EA, Russell KF, Heatherley L, Hoelzer DT, Maziasz PJ. 2003. Atom probe tomography of nanoscale particles in ODS ferritic alloys. Mater. Sci. Eng. A 353:140-45
-
(2003)
Mater. Sci. Eng. A
, vol.353
, pp. 140-145
-
-
Miller, M.K.1
Kenik, E.A.2
Russell, K.F.3
Heatherley, L.4
Hoelzer, D.T.5
Maziasz, P.J.6
-
110
-
-
0347590918
-
Effect of Ti and W on the mechanical properties and microstructure of 12% Cr base mechanical-alloyed nano-sized ODS ferritic alloys
-
Kim IS, Choi BY, Kang CY, Okuda T, Maziasz PJ, Miyahara K. 2003. Effect of Ti and W on the mechanical properties and microstructure of 12% Cr base mechanical-alloyed nano-sized ODS ferritic alloys. ISIJ Int. 43:1640-46
-
(2003)
ISIJ Int
, vol.43
, pp. 1640-1646
-
-
Kim, I.S.1
Choi, B.Y.2
Kang, C.Y.3
Okuda, T.4
Maziasz, P.J.5
Miyahara, K.6
-
111
-
-
3342960908
-
The development and stability of Y-Ti-O nanoclusters in mechanically alloyed Fe-Cr based ferritic alloys
-
Alinger MJ, Odette GR, Hoezler DT. 2004. The development and stability of Y-Ti-O nanoclusters in mechanically alloyed Fe-Cr based ferritic alloys. J. Nucl. Mater. 329-333:382-86
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 382-386
-
-
Alinger, M.J.1
Odette, G.R.2
Hoezler, D.T.3
-
114
-
-
3342967938
-
TEM examination of microstructural evolution during processing of 14CrYWTi nanostructured ferritic alloys
-
Kishimoto H, Alinger MJ, Odette GR, Yamamoto T. 2004. TEM examination of microstructural evolution during processing of 14CrYWTi nanostructured ferritic alloys. J. Nucl. Mater. 329-333:369-71
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 369-371
-
-
Kishimoto, H.1
Alinger, M.J.2
Odette, G.R.3
Yamamoto, T.4
-
115
-
-
50349099537
-
On the precipitation kinetics, thermal stability and strengthening mechanisms of nanometer scale Y-Ti-O clusters in nanostructured ferritic alloys
-
DOE, Oak Ridge, TN
-
Alinger MJ, Odette GR. 2005. On the precipitation kinetics, thermal stability and strengthening mechanisms of nanometer scale Y-Ti-O clusters in nanostructured ferritic alloys. Fusion Mater. Semiannu. Prog. Rep. DOE-ER-03 13/37 61-69, DOE, Oak Ridge, TN
-
(2005)
Fusion Mater. Semiannu. Prog. Rep. DOE-ER-03 13/37 61-69
-
-
Alinger, M.J.1
Odette, G.R.2
-
116
-
-
50349094094
-
On the role of alloy composition and processing variables in nanofeature formation and dispersion strengthening in nanostructured ferritic alloys
-
DOE, Oak Ridge, TN
-
Alinger MJ, Odette GR, Hoelzer DT. 2008. On the role of alloy composition and processing variables in nanofeature formation and dispersion strengthening in nanostructured ferritic alloys. Fusion Mater. Semiannu. Prog. Rep. DOE-ER-0313/43, DOE, Oak Ridge, TN
-
(2008)
Fusion Mater. Semiannu. Prog. Rep. DOE-ER-0313/43
-
-
Alinger, M.J.1
Odette, G.R.2
Hoelzer, D.T.3
-
117
-
-
18544364622
-
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys
-
Klueh RL, ShingledeckerJP, Swindeman RW, Hoelzer DT. 2005. Oxide dispersion-strengthened steels: a comparison of some commercial and experimental alloys. J. Nucl. Mater. 341:103-14
-
(2005)
J. Nucl. Mater
, vol.341
, pp. 103-114
-
-
Klueh, R.L.1
Shingledecker, J.P.2
Swindeman, R.W.3
Hoelzer, D.T.4
-
119
-
-
33744779623
-
Characterization of precipitates in MA/ODS ferritic alloys
-
Miller MK, Russell KF, Hoelzer DT. 2006. Characterization of precipitates in MA/ODS ferritic alloys. J. Nucl. Mater. 351:261-68
-
(2006)
J. Nucl. Mater
, vol.351
, pp. 261-268
-
-
Miller, M.K.1
Russell, K.F.2
Hoelzer, D.T.3
-
120
-
-
34447517480
-
Fracture toughness and tensile properties of nano-structured ferritic steel 12YWT
-
Sokolov MA, Hoelzer DT, Stoller RE, McClintock DA 2007. Fracture toughness and tensile properties of nano-structured ferritic steel 12YWT. J. Nucl. Mater. 367-370:213-16
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 213-216
-
-
Sokolov, M.A.1
Hoelzer, D.T.2
Stoller, R.E.3
McClintock, D.A.4
-
121
-
-
34447557725
-
Effects of consolidation temperature, strength, and microstructure on fracture toughness of nanostructured ferritic alloys
-
Miao P, Odette GR, Yamamoto T, Alinger MJ, Hoelzer D, Gragg D. 2007. Effects of consolidation temperature, strength, and microstructure on fracture toughness of nanostructured ferritic alloys. J. Nucl. Mater. 367-370:208-12
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 208-212
-
-
Miao, P.1
Odette, G.R.2
Yamamoto, T.3
Alinger, M.J.4
Hoelzer, D.5
Gragg, D.6
-
124
-
-
34447559917
-
Influence of particle dispersions on the high-temperature strength of ferritic alloys
-
Hoelzer DT, Bentley J, Sokolov MA, Miller MK, Odette GR, Alinger MJ. 2007. Influence of particle dispersions on the high-temperature strength of ferritic alloys. J. Nucl. Mater. 367-370:166-72
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 166-172
-
-
Hoelzer, D.T.1
Bentley, J.2
Sokolov, M.A.3
Miller, M.K.4
Odette, G.R.5
Alinger, M.J.6
-
125
-
-
34447532151
-
The microstructure and strength properties of MA957 nanostructured ferritic alloy joints produced by friction stir and electro-spark deposition welding
-
Miao P, Odette GR, Gould J, Bernath J, Miller R, et al. 2007. The microstructure and strength properties of MA957 nanostructured ferritic alloy joints produced by friction stir and electro-spark deposition welding. J. Nucl. Mater. 367-370:1197-1202
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 1197-1202
-
-
Miao, P.1
Odette, G.R.2
Gould, J.3
Bernath, J.4
Miller, R.5
-
126
-
-
0030261524
-
Microstructural examination of commercial ferritic alloys at 200 dpa
-
Gelles DS. 1996. Microstructural examination of commercial ferritic alloys at 200 dpa. J. Nucl. Mater. 233-237:293-98
-
(1996)
J. Nucl. Mater
, vol.233-237
, pp. 293-298
-
-
Gelles, D.S.1
-
127
-
-
0032182168
-
Irradiation creep of various ferritic alloys irradiated at 400°C in the PFR and FFTF reactors
-
Tolozcko MB, Garner FA, Eiholzer CR. 1998. Irradiation creep of various ferritic alloys irradiated at 400°C in the PFR and FFTF reactors. J. Nucl. Mater. 258-263:1163-66
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 1163-1166
-
-
Tolozcko, M.B.1
Garner, F.A.2
Eiholzer, C.R.3
-
129
-
-
3342893263
-
Irradiation creep and swelling from 400 to 600°C of the oxide dispersion strengthened ferritic alloy MA957
-
Tolozcko MB, Gelles DS, Garner FA Kurtz RJ, Abe K. 2004. Irradiation creep and swelling from 400 to 600°C of the oxide dispersion strengthened ferritic alloy MA957. J. Nucl. Mater. 329-333:352-55
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 352-355
-
-
Tolozcko, M.B.1
Gelles, D.S.2
Garner, F.A.3
Kurtz, R.J.4
Abe, K.5
-
130
-
-
27744573453
-
The stability of 9Cr-ODS oxide particles under heavy-ion irradiation
-
Allen TR, Gan J, Cole JI, Ukai S, Shutthanandan V, Thevuthasan S. 2005. The stability of 9Cr-ODS oxide particles under heavy-ion irradiation. J. Nucl. Sci. Eng. 151:305-12
-
(2005)
J. Nucl. Sci. Eng
, vol.151
, pp. 305-312
-
-
Allen, T.R.1
Gan, J.2
Cole, J.I.3
Ukai, S.4
Shutthanandan, V.5
Thevuthasan, S.6
-
131
-
-
34447500408
-
The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/dpa ratios and dpa rates
-
Yamamoto T, Odette GR, Miao P, Hoelzer DT, Bentley J, et al. 2007. The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/dpa ratios and dpa rates. J. Nucl. Mater. 367-370:399-410
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 399-410
-
-
Yamamoto, T.1
Odette, G.R.2
Miao, P.3
Hoelzer, D.T.4
Bentley, J.5
-
132
-
-
50349086548
-
-
Deleted in proof
-
Deleted in proof
-
-
-
-
133
-
-
50349098998
-
-
Rieth M, Schirra M, Falkenstein A, Graf P, Heger S, et al. 2003. Eurofer97 tensile, charpy, creep, and structural tests. Forsch. Karlsruhe FZKA6911
-
Rieth M, Schirra M, Falkenstein A, Graf P, Heger S, et al. 2003. Eurofer97 tensile, charpy, creep, and structural tests. Forsch. Karlsruhe FZKA6911
-
-
-
-
134
-
-
55249088819
-
-
Salston MC, Odette GR. 2008. A database and constitutive model for the static and creep strength of MA957 from room temperature to 1000°C. Trans. ANS 98:in press
-
Salston MC, Odette GR. 2008. A database and constitutive model for the static and creep strength of MA957 from room temperature to 1000°C. Trans. ANS 98:in press
-
-
-
-
136
-
-
0039853925
-
Threshold stresses for dislocation climb over hard particles: The effect of an attractive interaction
-
Arzt E, Wilkinson DS. 1986. Threshold stresses for dislocation climb over hard particles: the effect of an attractive interaction, Acta Metall. 34:1893-98
-
(1986)
Acta Metall
, vol.34
, pp. 1893-1898
-
-
Arzt, E.1
Wilkinson, D.S.2
-
137
-
-
0025415664
-
A new model-based creep equation for dispersion strengthened materials
-
Rosler J, Arzt E. 1990. A new model-based creep equation for dispersion strengthened materials. Acta Metall. Mater. 38:671-83
-
(1990)
Acta Metall. Mater
, vol.38
, pp. 671-683
-
-
Rosler, J.1
Arzt, E.2
-
138
-
-
0021465850
-
Diffusionally modified dislocation/particle elastic interactions
-
Srolovitz DJ, Luton MJ, Petkovic-Luton R, Barnett DM, Nix WD. 1984. Diffusionally modified dislocation/particle elastic interactions, Acta Metall. 32:1079-88
-
(1984)
Acta Metall
, vol.32
, pp. 1079-1088
-
-
Srolovitz, D.J.1
Luton, M.J.2
Petkovic-Luton, R.3
Barnett, D.M.4
Nix, W.D.5
-
139
-
-
0001616990
-
An empirical relationship between rupture life and minimum creep rate in creep-rupture tests
-
Monkman FC, Grant NJ. 1956. An empirical relationship between rupture life and minimum creep rate in creep-rupture tests. Proc. ASTM 56:593-20
-
(1956)
Proc. ASTM
, vol.56
, pp. 593-620
-
-
Monkman, F.C.1
Grant, N.J.2
-
140
-
-
0018515873
-
Intergranular fracture during power law creep
-
Edwards GH, Ashby MF. 1979. Intergranular fracture during power law creep. Acta Metall. 27:1505-18
-
(1979)
Acta Metall
, vol.27
, pp. 1505-1518
-
-
Edwards, G.H.1
Ashby, M.F.2
-
141
-
-
49649135775
-
On the coarsening of grain boundary precipitates
-
Ardell AJ. 1972. On the coarsening of grain boundary precipitates. Acta Metall. 20:601-9
-
(1972)
Acta Metall
, vol.20
, pp. 601-609
-
-
Ardell, A.J.1
-
142
-
-
55249116611
-
-
Miao P, Odette GR, Yamamoto T, Klingensmith D. 2008. On the thermal stability of 9% Cr tempered martensitic steels and nano-structured ferritic alloys. Trans. ANS 98:in press
-
Miao P, Odette GR, Yamamoto T, Klingensmith D. 2008. On the thermal stability of 9% Cr tempered martensitic steels and nano-structured ferritic alloys. Trans. ANS 98:in press
-
-
-
-
144
-
-
50349098787
-
-
Kaito T, Ohtsuka S, Inoue M, Asayama T, Uwaba T, Mizuta S, et al, 2007. In-pile creep rupture properties of ODS ferritic steel claddings. Presented at Int. Conf. Fusion React. Mater., 13th, Nice. J. Nucl. Mater. In press
-
Kaito T, Ohtsuka S, Inoue M, Asayama T, Uwaba T, Mizuta S, et al, 2007. In-pile creep rupture properties of ODS ferritic steel claddings. Presented at Int. Conf. Fusion React. Mater., 13th, Nice. J. Nucl. Mater. In press
-
-
-
-
145
-
-
34447544398
-
The transport and fate of helium, in martensitic steels at fusion relevant He/dpa ratios and dpa rates
-
Kurtz RJ, Odette GR, Yamamoto T, Gelles DS, Miao P, Oliver BM, 2007. The transport and fate of helium, in martensitic steels at fusion relevant He/dpa ratios and dpa rates. J. Nucl. Mater. 367-370:417-22
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 417-422
-
-
Kurtz, R.J.1
Odette, G.R.2
Yamamoto, T.3
Gelles, D.S.4
Miao, P.5
Oliver, B.M.6
-
146
-
-
55249091211
-
-
Odette GR, Miao P, Yamamoto T, Edwards D, Kurtz R, et al. 2008. A comparison of cavity formation in neutron irradiated nanostructured ferritic alloys and tempered martensitic steels at high He/dpa ratio. Trans. ANS 98:in press
-
Odette GR, Miao P, Yamamoto T, Edwards D, Kurtz R, et al. 2008. A comparison of cavity formation in neutron irradiated nanostructured ferritic alloys and tempered martensitic steels at high He/dpa ratio. Trans. ANS 98:in press
-
-
-
-
147
-
-
50349094846
-
-
Henry J, Avery X, Dia Y, Pizzanelli JP, Espinas JJ. 2008. Tensile properties of an ODS 14 Cr alloy irradiated in a spallation environment. Presented at Int. Conf. Fusion React. Mater., 13th, Nice. J. Nucl. Mater. In press
-
Henry J, Avery X, Dia Y, Pizzanelli JP, Espinas JJ. 2008. Tensile properties of an ODS 14 Cr alloy irradiated in a spallation environment. Presented at Int. Conf. Fusion React. Mater., 13th, Nice. J. Nucl. Mater. In press
-
-
-
-
148
-
-
55249089438
-
-
Yamamoto T, Dai Y, Odette GR, Salston M, Miao P. 2008. On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of 8Cr tempered martensitic steels: compilation and analysis of existing data. Trans. ANS 98:in press
-
Yamamoto T, Dai Y, Odette GR, Salston M, Miao P. 2008. On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of 8Cr tempered martensitic steels: compilation and analysis of existing data. Trans. ANS 98:in press
-
-
-
|