-
1
-
-
84865120266
-
Opportunities and challenges for a sustainable energy future
-
Chu S, Majumdar A. 2012. Opportunities and challenges for a sustainable energy future. Nature 488:294-303
-
(2012)
Nature
, vol.488
, pp. 294-303
-
-
Chu, S.1
Majumdar, A.2
-
2
-
-
84872712013
-
Materials challenges in nuclear energy
-
Zinkle SJ, Was GS. 2013. Materials challenges in nuclear energy. Acta Mater. 61:735-58
-
(2013)
Acta Mater
, vol.61
, pp. 735-758
-
-
Zinkle, S.J.1
Was, G.S.2
-
3
-
-
0016286523
-
Fusion reactors as future energy sources
-
Post RF, Ribe FL. 1974. Fusion reactors as future energy sources. Science 186:397-407
-
(1974)
Science
, vol.186
, pp. 397-407
-
-
Post, R.F.1
Ribe, F.L.2
-
4
-
-
84904005545
-
Nuclear fusion power
-
ed. RA Meyers New York: Academic. 3rd ed
-
Gordinier MR, Davis JW, Scott FR, Schultz KR. 2003. Nuclear fusion power. In Encyclopedia of Physical Science and Technology, Vol. 10, ed. RA Meyers, pp. 671-99. New York: Academic. 3rd ed.
-
(2003)
Encyclopedia of Physical Science and Technology
, vol.10
, pp. 671-699
-
-
Gordinier, M.R.1
Davis, J.W.2
Scott, F.R.3
Schultz, K.R.4
-
5
-
-
84872075018
-
Half a
-
century of fusion research towards ITER
-
Lehnert B. 2013. Half a century of fusion research towards ITER. Phys. Scr. 87:018201
-
(2013)
Phys. Scr
, vol.87
, pp. 018201
-
-
Lehnert, B.1
-
6
-
-
18544389058
-
Physics of magnetically confined plasmas
-
Boozer AH. 2004. Physics of magnetically confined plasmas. Rev. Mod. Phys. 76:1071-141
-
(2004)
Rev. Mod. Phys
, vol.76
, pp. 1071-1141
-
-
Boozer, A.H.1
-
7
-
-
65449152231
-
TheNational Ignition Facility: Ushering in a new age for high energy density science
-
Moses EI, Boyd RN, Remington BA, KeaneCJ, Al-Ayat R. 2009. TheNational Ignition Facility: ushering in a new age for high energy density science. Phys. Plasmas 16:041006
-
(2009)
Phys. Plasmas
, vol.16
, pp. 041006
-
-
Moses, E.I.1
Boyd, R.N.2
Remington, B.A.3
Keanecj Al-Ayat, R.4
-
8
-
-
57049161411
-
Review of blanket designs for advanced fusion reactors
-
Ihli T, Basu TK, Giancarli LM, Konishi S, Malang S, et al. 2008. Review of blanket designs for advanced fusion reactors. Fusion Eng. Des. 83:912-19
-
(2008)
Fusion Eng. des
, vol.83
, pp. 912-919
-
-
Ihli, T.1
Basu, T.K.2
Giancarli, L.M.3
Konishi, S.4
Malang, S.5
-
9
-
-
84865764018
-
Overview of the ITER TBM Program
-
Giancarli LM, Abdou M, Campbell DJ, Chuyanov VA, Ahn MY, et al. 2012. Overview of the ITER TBM Program. Fusion Eng. Des. 87:395-402
-
(2012)
Fusion Eng. des
, vol.87
, pp. 395-402
-
-
Giancarli, L.M.1
Abdou, M.2
Campbell, D.J.3
Chuyanov, V.A.4
Ahn, M.Y.5
-
10
-
-
84884885049
-
Multimodal options for materials research to advance the basis for fusion energy in the ITER era
-
Zinkle SJ, Möslang A, Muroga T, Tanigawa H. 2013. Multimodal options for materials research to advance the basis for fusion energy in the ITER era. Nucl. Fusion 53:104024
-
(2013)
Nucl. Fusion
, vol.53
, pp. 104024
-
-
Zinkle, S.J.1
Möslang, A.2
Muroga, T.3
Tanigawa, H.4
-
11
-
-
0029277901
-
The influence of small cracks in insulating coatings on the flow structure and pressure drop in MHD channel flows
-
Bühler L. 1995. The influence of small cracks in insulating coatings on the flow structure and pressure drop in MHD channel flows. Fusion Eng. Des. 27:650-58
-
(1995)
Fusion Eng. des
, vol.27
, pp. 650-658
-
-
Bühler, L.1
-
12
-
-
78650604812
-
Eurofer corrosion by the flow of the eutectic alloy Pb-Li in the presence of a strong magnetic field
-
Moreau R, Brechet Y, Maniguet L. 2011. Eurofer corrosion by the flow of the eutectic alloy Pb-Li in the presence of a strong magnetic field. Fusion Eng. Des. 86:106-20
-
(2011)
Fusion Eng. des
, vol.86
, pp. 106-120
-
-
Moreau, R.1
Brechet, Y.2
Maniguet, L.3
-
13
-
-
0029273164
-
Summary of experimental results for ceramic breeder materials
-
Roux N, Hollenberg G, Johnson C, Noda K, Verrall R. 1995. Summary of experimental results for ceramic breeder materials. Fusion Eng. Des. 27:154-66
-
(1995)
Fusion Eng. des
, vol.27
, pp. 154-166
-
-
Roux, N.1
Hollenberg, G.2
Johnson, C.3
Noda, K.4
Verrall, R.5
-
14
-
-
0032181762
-
The challenge of developing structural materials for fusion power systems
-
Bloom EE. 1998. The challenge of developing structural materials for fusion power systems. J. Nucl. Mater. 258-263:7-17
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 7-17
-
-
Bloom, E.E.1
-
15
-
-
3342889818
-
Materials to deliver the promise of fusion power-progress and challenges
-
Bloom EE, Zinkle SJ, Wiffen FW. 2004. Materials to deliver the promise of fusion power-progress and challenges. J. Nucl. Mater. 329-333:12-19
-
(2004)
J. Nucl. Mater
, vol.329-333
, pp. 12-19
-
-
Bloom, E.E.1
Zinkle, S.J.2
Wiffen, F.W.3
-
17
-
-
72149118461
-
Structural materials for fission and fusion energy
-
Zinkle SJ, Busby JT. 2009. Structural materials for fission and fusion energy. Mater. Today 12:12-19
-
(2009)
Mater. Today
, vol.12
, pp. 12-19
-
-
Zinkle, S.J.1
Busby, J.T.2
-
18
-
-
0023844122
-
Exploring the competitive potential of magnetic fusion energy-the interaction of economics with safety and environmental characteristics
-
Holdren JP, Berwald DH, Budnitz RJ, Crocker JG, Delene JG, et al. 1988. Exploring the competitive potential of magnetic fusion energy-the interaction of economics with safety and environmental characteristics. Fusion Technol. 13:7-56
-
(1988)
Fusion Technol
, vol.13
, pp. 7-56
-
-
Holdren, J.P.1
Berwald, D.H.2
Budnitz, R.J.3
Crocker, J.G.4
Delene, J.G.5
-
19
-
-
0017883577
-
Fusion energy in context: Its fitness for the long term
-
Holdren JP. 1978. Fusion energy in context: its fitness for the long term. Science 200:168-80
-
(1978)
Science
, vol.200
, pp. 168-180
-
-
Holdren, J.P.1
-
20
-
-
0001925102
-
Low activation materials for fusion applications
-
Bloom EE, Conn RW, Davis JW, Gold RE, Little R, et al. 1984. Low activation materials for fusion applications. J. Nucl. Mater. 122-123:17-26
-
(1984)
J. Nucl. Mater
, vol.122-123
, pp. 17-26
-
-
Bloom, E.E.1
Conn, R.W.2
Davis, J.W.3
Gold, R.E.4
Little, R.5
-
21
-
-
0025796498
-
Initial integration of accident safety, waste management, recycling, effluent, and maintenance considerations for low-activation materials
-
Piet SJ, Cheng ET, Fetter S, Herring JS. 1991. Initial integration of accident safety, waste management, recycling, effluent, and maintenance considerations for low-activation materials. Fusion Technol. 19:146-61
-
(1991)
Fusion Technol
, vol.19
, pp. 146-161
-
-
Piet, S.J.1
Cheng, E.T.2
Fetter, S.3
Herring, J.S.4
-
22
-
-
0032179894
-
Concentration limits of natural elements in low activation fusion materials
-
Cheng ET. 1998. Concentration limits of natural elements in low activation fusion materials. J. Nucl. Mater. 258-263:1767-72
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 1767-1772
-
-
Cheng, E.T.1
-
23
-
-
13444301419
-
Reduced-activation bainitic and martensitic steels for nuclear fusion applications
-
Klueh RL. 2004. Reduced-activation bainitic and martensitic steels for nuclear fusion applications. Curr. Opin. Solid State Mater. Sci. 8:239-50
-
(2004)
Curr. Opin. Solid State Mater. Sci
, vol.8
, pp. 239-250
-
-
Klueh, R.L.1
-
24
-
-
80053597507
-
Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket
-
Tanigawa H, Shiba K, Möslang A, Stoller RE, Lindau R, et al. 2011. Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket. J. Nucl. Mater. 417:9-15
-
(2011)
J. Nucl. Mater
, vol.417
, pp. 9-15
-
-
Tanigawa, H.1
Shiba, K.2
Möslang, A.3
Stoller, R.E.4
Lindau, R.5
-
25
-
-
0036942168
-
Perspective ofODSalloys application in nuclear environments
-
Ukai S, Fujiwara M. 2002. Perspective ofODSalloys 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
-
26
-
-
18544364622
-
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys
-
Klueh RL, Shingledecker JP, 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
-
27
-
-
27844465405
-
Present development status of EUROFER and ODS for application in blanket concepts
-
Lindau R, Möslang A, Rieth M, Klimankou M, Materna-Morris E, et al. 2005. Present development status of EUROFER and ODS for application in blanket concepts. Fusion Eng. Des. 75-79:989-96
-
(2005)
Fusion Eng. des
, vol.75-79
, pp. 989-996
-
-
Lindau, R.1
Möslang, A.2
Rieth, M.3
Klimankou, M.4
Materna-Morris, E.5
-
28
-
-
27844479222
-
Advanced materials for fusion technology
-
Zinkle SJ. 2005. Advanced materials for fusion technology. Fusion Eng. Des. 74:31-40
-
(2005)
Fusion Eng. des
, vol.74
, pp. 31-40
-
-
Zinkle, S.J.1
-
29
-
-
0032178502
-
Materials integration issues for highperformance fusion power systems
-
Smith DL, Billone MC, Majumdar S, Mattas RF, Sze D-K. 1998. Materials integration issues for highperformance fusion power systems. J. Nucl. Mater. 258-263:65-73
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 65-73
-
-
Smith, D.L.1
Billone, M.C.2
Majumdar, S.3
Mattas, R.F.4
Sze, D.-K.5
-
30
-
-
18144441331
-
Research and development on vanadium alloys for fusion applications
-
Zinkle SJ, Matsui H, Smith DL, Rowcliffe AF, van Osch E, et al. 1998. Research and development on vanadium alloys for fusion applications. J. Nucl. Mater. 258-263:205-14
-
(1998)
J. Nucl. Mater
, vol.258-263
, pp. 205-214
-
-
Zinkle, S.J.1
Matsui, H.2
Smith, D.L.3
Rowcliffe, A.F.4
Van Osch, E.5
-
31
-
-
34447574694
-
Review of advances in development of vanadium alloys and MHD insulator coatings
-
Muroga T, Chen JM, Chernov VM, Fukumoto K, Hoelzer DT, et al. 2007. Review of advances in development of vanadium alloys and MHD insulator coatings. J. Nucl. Mater. 367-370:780-87
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 780-787
-
-
Muroga, T.1
Chen, J.M.2
Chernov, V.M.3
Fukumoto, K.4
Hoelzer, D.T.5
-
32
-
-
80053579163
-
Silicon carbide composites as fusion power reactor structural materials
-
Snead LL, Nozawa T, Ferraris M, Katoh Y, Shinavski R, Sawan M. 2011. Silicon carbide composites as fusion power reactor structural materials. J. Nucl. Mater. 417:330-39
-
(2011)
J. Nucl. Mater
, vol.417
, pp. 330-339
-
-
Snead, L.L.1
Nozawa, T.2
Ferraris, M.3
Katoh, Y.4
Shinavski, R.5
Sawan, M.6
-
33
-
-
79958799225
-
Physics basis and design of the ITER plasma-facing components
-
Pitts RA, Carpentier S, Escourbiac F, Hirai T, Komarov V, et al. 2011. Physics basis and design of the ITER plasma-facing components. J. Nucl. Mater. 415:S957-64
-
(2011)
J. Nucl. Mater
, vol.415
-
-
Pitts, R.A.1
Carpentier, S.2
Escourbiac, F.3
Hirai, T.4
Komarov, V.5
-
34
-
-
79956124784
-
Fusion materials modeling: Challenges and opportunities
-
Wirth BD, Nordlund K, Whyte DG, Xu D. 2011. Fusion materials modeling: challenges and opportunities. MRS Bull. 36:216-22
-
(2011)
MRS Bull
, vol.36
, pp. 216-222
-
-
Wirth, B.D.1
Nordlund, K.2
Whyte, D.G.3
Xu, D.4
-
35
-
-
84859060449
-
High heat flux performance of plasma facing materials and components under service conditions in future fusion reactors
-
Linke J. 2012. High heat flux performance of plasma facing materials and components under service conditions in future fusion reactors. Fusion Sci. Technol. 61:246-55
-
(2012)
Fusion Sci. Technol
, vol.61
, pp. 246-255
-
-
Linke, J.1
-
36
-
-
0346035790
-
Plasma facing and high heat flux materials-needs for ITER and beyond
-
Bolt H, Barabash VR, Federici G, Linke J, Loarte A, et al. 2002. Plasma facing and high heat flux materials-needs for ITER and beyond. J. Nucl. Mater. 307-311:43-52
-
(2002)
J. Nucl. Mater
, vol.307-311
, pp. 43-52
-
-
Bolt, H.1
Barabash, V.R.2
Federici, G.3
Linke, J.4
Loarte, A.5
-
37
-
-
83755163016
-
Preparing the scientific basis for an all metal ITER
-
Neu R. 2011. Preparing the scientific basis for an all metal ITER. Plasma Phys. Control. Fusion 53:124040
-
(2011)
Plasma Phys. Control. Fusion
, vol.53
, pp. 124040
-
-
Neu, R.1
-
38
-
-
84988385351
-
Overview of the JET results with the ITER-like wall
-
Romanelli F. 2013. Overview of the JET results with the ITER-like wall. Nucl. Fusion 53:104002
-
(2013)
Nucl. Fusion
, vol.53
, pp. 104002
-
-
Romanelli, F.1
-
39
-
-
0037345079
-
Material/plasma surface interaction issues following neutron damage
-
Barabash V, Federici G, Linke J, Wu C.H. 2003. Material/plasma surface interaction issues following neutron damage. J. Nucl. Mater. 313:42-51
-
(2003)
J. Nucl. Mater
, vol.313
, pp. 42-51
-
-
Barabash, V.1
Federici, G.2
Linke, J.3
Wu, C.H.4
-
40
-
-
80053596825
-
Making tungsten work
-
Nygren RE, Raffray R, Whyte D, Ulrickson MA, Baldwin M, Snead LL. 2011. Making tungsten work. J. Nucl. Mater. 417:451-56
-
(2011)
J. Nucl. Mater
, vol.417
, pp. 451-456
-
-
Nygren, R.E.1
Raffray, R.2
Whyte, D.3
Ulrickson, M.A.4
Baldwin, M.5
Snead, L.L.6
-
41
-
-
84868241355
-
Recent progress in research on tungsten materials for nuclear fusion applications in Europe
-
Rieth M, Dudarev SL, Gonzalez de Vicente SM, Aktaa J, Ahlgren R, et al. 2013. Recent progress in research on tungsten materials for nuclear fusion applications in Europe. J. Nucl. Mater. 432:482-500
-
(2013)
J. Nucl. Mater
, vol.432
, pp. 482-500
-
-
Rieth, M.1
Dudarev, S.L.2
Gonzalez De Vicente, S.M.3
Aktaa, J.4
Ahlgren, R.5
-
42
-
-
18144446790
-
Transmutation of Mo, Re, W, Hf and v in various irradiation test facilities and STARFIRE
-
Greenwood LR, Garner FA. 1994. Transmutation of Mo, Re, W, Hf and V in various irradiation test facilities and STARFIRE. J. Nucl. Mater. 212-215:635-39
-
(1994)
J. Nucl. Mater
, vol.212-215
, pp. 635-639
-
-
Greenwood, L.R.1
Garner, F.A.2
-
43
-
-
84903989325
-
The effects of helium in irradiated structural alloys
-
Dai Y, Odette GR, Yamamoto T. 2012. The effects of helium in irradiated structural alloys. See Ref. 153, pp. 141-93
-
(2012)
See Ref
, vol.153
, pp. 141-193
-
-
Dai, Y.1
Odette, G.R.2
Yamamoto, T.3
-
44
-
-
0344927925
-
Helium accumulation in metals during irradiation-where do we stand?
-
Trinkaus H, Singh BN. 2003. Helium accumulation in metals during irradiation-where do we stand? J. Nucl. Mater. 323:229-42
-
(2003)
J. Nucl. Mater
, vol.323
, pp. 229-242
-
-
Trinkaus, H.1
Singh, B.N.2
-
45
-
-
84885292066
-
Evaluation of irradiation facility options for fusion materials research and development
-
Zinkle SJ, Möslang A. 2013. Evaluation of irradiation facility options for fusion materials research and development. Fusion Eng. Des. 88:472-82
-
(2013)
Fusion Eng. des
, vol.88
, pp. 472-482
-
-
Zinkle, S.J.1
Möslang, A.2
-
46
-
-
84903986603
-
Radiation-induced effects on microstructure
-
Zinkle SJ. 2012. Radiation-induced effects on microstructure. See Ref. 153, pp. 65-98
-
(2012)
See Ref
, vol.153
, pp. 65-98
-
-
Zinkle, S.J.1
-
47
-
-
0343462030
-
Interpretation of defect reactions in irradiated metals by the one interstitial model
-
Rep. CONF- 751006-P1, ed. MT Robinson, FWYoung Jr Springfield, VA: Natl. Tech. Inf. Serv
-
Schilling W, Ehrhart P, Sonnenberg K. 1975. Interpretation of defect reactions in irradiated metals by the one interstitial model. In Fundamental Aspects of Radiation Damage in Metals, Vol. I, Rep. CONF- 751006-P1, ed. MT Robinson, FWYoung Jr, pp. 470-92. Springfield, VA: Natl. Tech. Inf. Serv.
-
(1975)
Fundamental Aspects of Radiation Damage in Metals
, vol.1
, pp. 470-492
-
-
Schilling, W.1
Ehrhart, P.2
Sonnenberg, K.3
-
48
-
-
0000434255
-
Recovery of irradiated and quenched metals
-
Schilling W, Sonnenberg K. 1973. Recovery of irradiated and quenched metals. J. Phys. F 3:322-50
-
(1973)
J. Phys F
, vol.3
, pp. 322-350
-
-
Schilling, W.1
Sonnenberg, K.2
-
49
-
-
0033746607
-
Models and mechanisms of irradiation-induced amorphization in ceramics
-
Weber WJ. 2000. Models and mechanisms of irradiation-induced amorphization in ceramics. Nucl. Instrum. Methods Phys. Res. B 166:98-106
-
(2000)
Nucl. Instrum. Methods Phys. Res.B
, vol.166
, pp. 98-106
-
-
Weber, W.J.1
-
50
-
-
58149210068
-
Radiation damage problems in high power spallation neutron sources
-
Ullmaier H, Carsughi F. 1995. Radiation damage problems in high power spallation neutron sources. Nucl. Instrum. Methods Phys. Res. B 101:406-21
-
(1995)
Nucl. Instrum. Methods Phys. Res.B
, vol.101
, pp. 406-421
-
-
Ullmaier, H.1
Carsughi, F.2
-
51
-
-
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
-
52
-
-
0345359310
-
Cleavage fracture and irradiation embrittlement of fusion reactor alloys: Mechanisms, multiscale models, toughness measurements and implications to structural integrity assessment
-
Odette GR, Yamamoto T, Rathbun HJ, He MY, Hribernik ML, Rensman JW. 2003. Cleavage fracture and irradiation embrittlement of fusion reactor alloys: mechanisms, multiscale models, toughness measurements and implications to structural integrity assessment. J. Nucl. Mater. 323:313-40
-
(2003)
J. Nucl. Mater
, vol.323
, pp. 313-340
-
-
Odette, G.R.1
Yamamoto, T.2
Rathbun, H.J.3
He, M.Y.4
Hribernik, M.L.5
Rensman, J.W.6
-
53
-
-
0001533897
-
Helium and hydrogen effects on the embrittlement of iron- and nickelbased alloys
-
Schroeder H, Ullmaier H. 1991. Helium and hydrogen effects on the embrittlement of iron- and nickelbased alloys. J. Nucl. Mater. 179-181:118-24
-
(1991)
J. Nucl. Mater
, vol.179-181
, pp. 118-124
-
-
Schroeder, H.1
Ullmaier, H.2
-
54
-
-
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
-
55
-
-
0028516215
-
Theory and experimental background on dimensional changes in irradiated alloys
-
Mansur LK. 1994. Theory and experimental background on dimensional changes in irradiated alloys. J. Nucl. Mater. 216:97-123
-
(1994)
J. Nucl. Mater
, vol.216
, pp. 97-123
-
-
Mansur, L.K.1
-
56
-
-
0024888189
-
Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels
-
Maziasz PJ. 1989. Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels. J. Nucl. Mater. 169:95-115
-
(1989)
J. Nucl. Mater
, vol.169
, pp. 95-115
-
-
Maziasz, P.J.1
-
57
-
-
0018503777
-
Radiation-induced segregation in binary and ternary alloys
-
Okamoto PR, Rehn LE. 1979. Radiation-induced segregation in binary and ternary alloys. J. Nucl. Mater. 83:2-23
-
(1979)
J. Nucl. Mater
, vol.83
, pp. 2-23
-
-
Okamoto, P.R.1
Rehn, L.E.2
-
58
-
-
17544402245
-
Control of helium effects in irradiated materials based on theory and experiment
-
Mansur LK, Lee EH, Maziasz PJ, Rowcliffe AF. 1986. Control of helium effects in irradiated materials based on theory and experiment. J. Nucl. Mater. 141-143:633-46
-
(1986)
J. Nucl. Mater
, vol.141-143
, pp. 633-646
-
-
Mansur, L.K.1
Lee, E.H.2
Maziasz, P.J.3
Rowcliffe, A.F.4
-
59
-
-
0025510452
-
The influence of helium on microstructural evolution: Implications for DT fusion reactors
-
Stoller RE. 1990. The influence of helium on microstructural evolution: implications for DT fusion reactors. J. Nucl. Mater. 174:289-310
-
(1990)
J. Nucl. Mater
, vol.174
, pp. 289-310
-
-
Stoller, R.E.1
-
60
-
-
0037501530
-
Swelling behavior of F82H steel irradiated by triple/dual ion beams
-
Wakai E, Kikuchi K, Yamamoto S, Aruga T, Ando M, et al. 2002. Swelling behavior of F82H steel irradiated by triple/dual ion beams. J. Nucl. Mater. 318:267-73
-
(2002)
J. Nucl. Mater
, vol.318
, pp. 267-273
-
-
Wakai, E.1
Kikuchi, K.2
Yamamoto, S.3
Aruga, T.4
Ando, M.5
-
61
-
-
0030218133
-
Influence of irradiation spectrum and implanted ions on the amorphization of ceramics
-
Zinkle SJ, Snead LL. 1996. Influence of irradiation spectrum and implanted ions on the amorphization of ceramics. Nucl. Instrum. Methods Phys. Res. B 116:92-101
-
(1996)
Nucl. Instrum. Methods Phys. Res.B
, vol.116
, pp. 92-101
-
-
Zinkle, S.J.1
Snead, L.L.2
-
62
-
-
10844254048
-
Understanding resistance to amorphization by radiation damage
-
Trachenko K. 2004. Understanding resistance to amorphization by radiation damage. J. Phys. Condens. Matter 16:R1491-515
-
(2004)
J. Phys. Condens. Matter
, vol.16
-
-
Trachenko, K.1
-
64
-
-
0034546452
-
Impact of irradiation effects on design solutions for ITER diagnostics
-
Yamamoto S, Shikama T, Belyakov V, Farnum E, Hodgson E, et al. 2000. Impact of irradiation effects on design solutions for ITER diagnostics. J. Nucl. Mater. 283-287:60-69
-
(2000)
J. Nucl. Mater
, vol.283-287
, pp. 60-69
-
-
Yamamoto, S.1
Shikama, T.2
Belyakov, V.3
Farnum, E.4
Hodgson, E.5
-
66
-
-
0026926376
-
Radiation-induced changes in the physical properties of ceramic materials
-
Zinkle SJ, Hodgson ER. 1992. Radiation-induced changes in the physical properties of ceramic materials. J. Nucl. Mater. 191-194:58-66
-
(1992)
J. Nucl. Mater
, vol.191-194
, pp. 58-66
-
-
Zinkle, S.J.1
Hodgson, E.R.2
-
68
-
-
0032480081
-
Japanese contribution to ITER task of irradiation tests on diagnostics components
-
Nishitani T, Ishitsuka E, Kakuta T, Sagawa H, Noda K, et al. 1998. Japanese contribution to ITER task of irradiation tests on diagnostics components. Fusion Eng. Des. 42:443-48
-
(1998)
Fusion Eng. des
, vol.42
, pp. 443-448
-
-
Nishitani, T.1
Ishitsuka, E.2
Kakuta, T.3
Sagawa, H.4
Noda, K.5
-
69
-
-
69549126746
-
Irradiation effects on dielectric mirrors for fusion power reactor application
-
Snead LL, Leonard KJ, Jellison GE, Sawan M, Lehecka T. 2009. Irradiation effects on dielectric mirrors for fusion power reactor application. Fusion Sci. Technol. 56:1069-77
-
(2009)
Fusion Sci. Technol
, vol.56
, pp. 1069-1077
-
-
Snead, L.L.1
Leonard, K.J.2
Jellison, G.E.3
Sawan, M.4
Lehecka, T.5
-
70
-
-
0035723277
-
Radiation effect in silica optical fiber exposed to intense mixed neutron-gamma radiation field
-
Brichard B, Borgermans P, Fernandez AF, Lammens K, Decreton M. 2001. Radiation effect in silica optical fiber exposed to intense mixed neutron-gamma radiation field. IEEE Trans. Nucl. Sci. 48:2069-73
-
(2001)
IEEE Trans Nucl. Sci
, vol.48
, pp. 2069-2073
-
-
Brichard, B.1
Borgermans, P.2
Fernandez, A.F.3
Lammens, K.4
Decreton, M.5
-
71
-
-
33847638789
-
Radiation-induced amorphization resistance and radiation tolerance in structurally related oxides
-
Sickafus KE, Grimes RW, Valdez JA, Cleave A, Tang M, et al. 2007. Radiation-induced amorphization resistance and radiation tolerance in structurally related oxides. Nat. Mater. 6:217-23
-
(2007)
Nat. Mater
, vol.6
, pp. 217-223
-
-
Sickafus, K.E.1
Grimes, R.W.2
Valdez, J.A.3
Cleave, A.4
Tang, M.5
-
72
-
-
49649154417
-
The effect of thermo-mechanical treatments on void formation in irradiated stainless steel
-
Stiegler JO, Bloom EE. 1971. The effect of thermo-mechanical treatments on void formation in irradiated stainless steel. J. Nucl. Mater. 41:341-44
-
(1971)
J. Nucl. Mater
, vol.41
, pp. 341-344
-
-
Stiegler, J.O.1
Bloom, E.E.2
-
73
-
-
26644441097
-
Stress-affected microstructural development and the creep-swelling interrelationship
-
Brager HR, Garner FA, Gilbert ER, Flinn JE, Wolfer WG. 1977. Stress-affected microstructural development and the creep-swelling interrelationship. See Ref. 154, pp. 727-55
-
(1977)
See Ref
, vol.154
, pp. 727-755
-
-
Brager, H.R.1
Garner, F.A.2
Gilbert, E.R.3
Flinn, J.E.4
Wolfer, W.G.5
-
74
-
-
0027906638
-
Dose dependence of the microstructural evolution in neutronirradiated austenitic stainless steel
-
Zinkle SJ, Maziasz PJ, Stoller RE. 1993. Dose dependence of the microstructural evolution in neutronirradiated austenitic stainless steel. J. Nucl. Mater. 206:266-86
-
(1993)
J. Nucl. Mater
, vol.206
, pp. 266-286
-
-
Zinkle, S.J.1
Maziasz, P.J.2
Stoller, R.E.3
-
75
-
-
0342316588
-
Effects of alloy composition on void swelling
-
Bates JF, JohnstonWG. 1977. Effects of alloy composition on void swelling. See Ref. 154, pp. 625-44
-
(1977)
See Ref
, vol.154
, pp. 625-644
-
-
Bates, J.F.1
Johnston, W.G.2
-
76
-
-
0017632710
-
The influence of fast diffusing substitutional elements on the swelling behaviour of Ni- and Cu-alloys
-
Venker H, Giesecke P, Ehrlich K. 1977. The influence of fast diffusing substitutional elements on the swelling behaviour of Ni- and Cu-alloys. See Ref. 154, pp. 415-20
-
(1977)
See Ref
, vol.154
, pp. 415-420
-
-
Venker, H.1
Giesecke, P.2
Ehrlich, K.3
-
77
-
-
49849111144
-
A comparison of irradiation-induced swelling and void formation in two austenitic stainless steels
-
Bloom EE, Stiegler JO. 1970. A comparison of irradiation-induced swelling and void formation in two austenitic stainless steels. J. Nucl. Mater. 35:244-46
-
(1970)
J. Nucl. Mater
, vol.35
, pp. 244-246
-
-
Bloom, E.E.1
Stiegler, J.O.2
-
78
-
-
0020745862
-
Swelling and swelling resistance possibilities of austenitic stainless steels in fusion reactors
-
Maziasz PJ. 1984. Swelling and swelling resistance possibilities of austenitic stainless steels in fusion reactors. J. Nucl. Mater. 122-123:472-86
-
(1984)
J. Nucl. Mater
, vol.122-123
, pp. 472-486
-
-
Maziasz, P.J.1
-
79
-
-
0019675817
-
Fission neutron damage rates and efficiencies in several metals
-
Klabunde CE, Coltman RR Jr. 1982. Fission neutron damage rates and efficiencies in several metals. J. Nucl. Mater. 108-109:183-93
-
(1982)
J. Nucl. Mater
, vol.108-109
, pp. 183-193
-
-
Klabunde, C.E.1
Coltman, Jr.R.R.2
-
80
-
-
0024011786
-
Defect production rates in metals by reactor neutron irradiation at 4.6 K
-
Wallner G, AnandMS, Greenwood LR, KirkMA, Mansel W, WaschkowskiW. 1988. Defect production rates in metals by reactor neutron irradiation at 4.6 K. J. Nucl. Mater. 152:146-53
-
(1988)
J. Nucl. Mater
, vol.152
, pp. 146-153
-
-
Wallner, G.1
Anand, M.S.2
Greenwood, L.R.3
Kirk, M.A.4
Mansel, W.5
Waschkowski, W.6
-
81
-
-
3342888978
-
Low-dose neutron irradiation damage in FCC and BCC metals
-
English CA. 1982. Low-dose neutron irradiation damage in FCC and BCC metals. J. Nucl. Mater. 108-109:104-23
-
(1982)
J. Nucl. Mater
, vol.108-109
, pp. 104-123
-
-
English, C.A.1
-
83
-
-
0033877090
-
The primary damage state in fcc, bcc and hcp metals as seen in molecular dynamics simulations
-
Bacon DJ, Gao F, Osetsky YN. 2000. The primary damage state in fcc, bcc and hcp metals as seen in molecular dynamics simulations. J. Nucl. Mater. 276:1-12
-
(2000)
J. Nucl. Mater
, vol.276
, pp. 1-12
-
-
Bacon, D.J.1
Gao, F.2
Osetsky, Y.N.3
-
84
-
-
84880214255
-
Density functional theory models for radiation damage
-
Dudarev SL. 2013. Density functional theory models for radiation damage. Annu. Rev. Mater. Res. 43:35-61
-
(2013)
Annu. Rev. Mater. Res
, vol.43
, pp. 35-61
-
-
Dudarev, S.L.1
-
86
-
-
0026926862
-
Effect of solute addition on swelling of vanadium after FFTF irradiation
-
Nakajima H, Yoshida S, Kohno Y, Matsui H. 1992. Effect of solute addition on swelling of vanadium after FFTF irradiation. J. Nucl. Mater. 191-194:952-55
-
(1992)
J. Nucl. Mater
, vol.191-194
, pp. 952-955
-
-
Nakajima, H.1
Yoshida, S.2
Kohno, Y.3
Matsui, H.4
-
87
-
-
43249129198
-
Effects of undersized Fe atoms on the stability of interstitials near a dislocation core in v studied by molecular dynamics simulation
-
Abe Y, Matsui H. 2007. Effects of undersized Fe atoms on the stability of interstitials near a dislocation core in V studied by molecular dynamics simulation. J. Comp. Aided Mater. Des. 14:121-27
-
(2007)
J. Comp. Aided Mater. des
, vol.14
, pp. 121-127
-
-
Abe, Y.1
Matsui, H.2
-
88
-
-
2942717044
-
Nanostructured high-entropy alloys with multiple principal elements: Novel alloy design concepts and outcomes
-
Yeh JW, Chen SK, Lin SJ, Gan JY, Chin TS, et al. 2004. Nanostructured high-entropy alloys with multiple principal elements: novel alloy design concepts and outcomes. Adv. Eng. Mater. 6:299-303
-
(2004)
Adv. Eng. Mater
, vol.6
, pp. 299-303
-
-
Yeh, J.W.1
Chen, S.K.2
Lin, S.J.3
Gan, J.Y.4
Chin, T.S.5
-
90
-
-
0034604486
-
Radiation tolerance of complex oxides
-
Sickafus KE, Minervini L, Grimes RW, Valdez JA, Ishimaru M, et al. 2000. Radiation tolerance of complex oxides. Science 289:748-51
-
(2000)
Science
, vol.289
, pp. 748-751
-
-
Sickafus, K.E.1
Minervini, L.2
Grimes, R.W.3
Valdez, J.A.4
Ishimaru, M.5
-
91
-
-
0033907537
-
Stabilization of metallic supercooled liquid and bulk amorphous alloys
-
Inoue A. 2000. Stabilization of metallic supercooled liquid and bulk amorphous alloys. Acta Mater. 48:279-306
-
(2000)
Acta Mater
, vol.48
, pp. 279-306
-
-
Inoue, A.1
-
92
-
-
36149002248
-
Fast-neutron-induced changes in quartz and vitreous silica
-
Primak W. 1958. Fast-neutron-induced changes in quartz and vitreous silica. Phys. Rev. 110:1240-54
-
(1958)
Phys. Rev
, vol.110
, pp. 1240-1254
-
-
Primak, W.1
-
93
-
-
0031213350
-
Radiation effects in glasses used for immobilization of high level waste and plutonium disposition
-
Weber WJ, Ewing RC, Angell CA, Arnold GW, Cormack AN, et al. 1997. Radiation effects in glasses used for immobilization of high level waste and plutonium disposition. J. Mater. Res. 12:1946-75
-
(1997)
J. Mater. Res
, vol.12
, pp. 1946-1975
-
-
Weber, W.J.1
Ewing, R.C.2
Angell, C.A.3
Arnold, G.W.4
Cormack, A.N.5
-
94
-
-
3042643627
-
Spontaneous recombination volumes of Frenkel defects in neutron-irradiated non-FCC metals
-
Nakagawa M, Mansel W, Boning K, Rosner P, Vogl G. 1979. Spontaneous recombination volumes of Frenkel defects in neutron-irradiated non-FCC metals. Phys. Rev. B 19:742-48
-
(1979)
Phys. Rev.B
, vol.19
, pp. 742-748
-
-
Nakagawa, M.1
Mansel, W.2
Boning, K.3
Rosner, P.4
Vogl, G.5
-
95
-
-
0019565665
-
Damage saturation effects on volume and resistivity changes induced by fission-fragment irradiation of copper
-
Birtcher RC, Blewitt TH. 1981. Damage saturation effects on volume and resistivity changes induced by fission-fragment irradiation of copper. J. Nucl. Mater. 98:63-70
-
(1981)
J. Nucl. Mater
, vol.98
, pp. 63-70
-
-
Birtcher, R.C.1
Blewitt, T.H.2
-
96
-
-
0024011605
-
Cascade damage in nickel-production, saturation and recovery
-
Birtcher RC, Blewitt TH. 1988. Cascade damage in nickel-production, saturation and recovery. J. Nucl. Mater. 152:204-11
-
(1988)
J. Nucl. Mater
, vol.152
, pp. 204-211
-
-
Birtcher, R.C.1
Blewitt, T.H.2
-
97
-
-
0030661091
-
Ion beam induced amorphization of crystalline solids: Mechanisms and modeling
-
Trinkaus H. 1997. Ion beam induced amorphization of crystalline solids: mechanisms and modeling. Mater. Sci. Forum 248-249:3-12
-
(1997)
Mater. Sci. Forum
, vol.248-249
, pp. 3-12
-
-
Trinkaus, H.1
-
98
-
-
30244478699
-
Irradiation damage to sintered beryllium oxide as a function of fast-neutron dose and flux at 110, 650, and 1100°C
-
Keilholtz GW, Lee JE Jr, Moore RE. 1966. Irradiation damage to sintered beryllium oxide as a function of fast-neutron dose and flux at 110, 650, and 1100°C. Nucl. Sci. Eng. 26:329-38
-
(1966)
Nucl. Sci. Eng
, vol.26
, pp. 329-338
-
-
Keilholtz, G.W.1
Lee, Jr.J.E.2
Moore, R.E.3
-
99
-
-
0002944345
-
Neutron-induced damage in BeO, Al2O3 andMgO-areview
-
Wilks RS. 1968. Neutron-induced damage in BeO, Al2O3 andMgO-areview. J. Nucl. Mater. 26:137-73
-
(1968)
J. Nucl. Mater
, vol.26
, pp. 137-173
-
-
Wilks, R.S.1
-
100
-
-
69649103280
-
Operating temperature window for SiC ceramics and composites for fusion energy applications
-
Katoh Y, Snead LL. 2009. Operating temperature window for SiC ceramics and composites for fusion energy applications. Fusion Sci. Technol. 56:1045-52
-
(2009)
Fusion Sci. Technol
, vol.56
, pp. 1045-1052
-
-
Katoh, Y.1
Snead, L.L.2
-
101
-
-
0015600853
-
Fast-neutron damage to polycrystalline alumina at temperatures from 60 to 1230°C
-
Keilholtz GW, Moore RE, Robertson HE. 1973. Fast-neutron damage to polycrystalline alumina at temperatures from 60 to 1230°C. Nucl. Technol. 17:234-46
-
(1973)
Nucl. Technol
, vol.17
, pp. 234-246
-
-
Keilholtz, G.W.1
Moore, R.E.2
Robertson, H.E.3
-
102
-
-
80053614484
-
Stability of SiC and its composites at high neutron fluence
-
Katoh Y, Nozawa T, Snead LL, Ozawa K, Tanigawa H. 2011. Stability of SiC and its composites at high neutron fluence. J. Nucl. Mater. 417:400-5
-
(2011)
J. Nucl. Mater
, vol.417
, pp. 400-405
-
-
Katoh, Y.1
Nozawa, T.2
Snead, L.L.3
Ozawa, K.4
Tanigawa, H.5
-
104
-
-
84875208474
-
The contribution made by lattice vacancies to the Wigner effect in radiation-damaged graphite
-
Latham CD, Heggie MI, Alatalo M, Oberg S, Briddon PR. 2013. The contribution made by lattice vacancies to the Wigner effect in radiation-damaged graphite. J. Phys. Condens. Matter 25:135403
-
(2013)
J. Phys. Condens. Matter
, vol.25
, pp. 135403
-
-
Latham, C.D.1
Heggie, M.I.2
Alatalo, M.3
Oberg, S.4
Briddon, P.R.5
-
105
-
-
34447506420
-
Swelling of SiC at intermediate and high irradiation temperatures
-
Snead LL, Katoh Y, Connery S. 2007. Swelling of SiC at intermediate and high irradiation temperatures. J. Nucl. Mater. 367-370:677-84
-
(2007)
J. Nucl. Mater
, vol.367-370
, pp. 677-684
-
-
Snead, L.L.1
Katoh, Y.2
Connery, S.3
-
106
-
-
0015385231
-
The rate theory of swelling due to void growth in irradiated metals
-
Brailsford AD, Bullough R. 1972. The rate theory of swelling due to void growth in irradiated metals. J. Nucl. Mater. 44:121-35
-
(1972)
J. Nucl. Mater
, vol.44
, pp. 121-135
-
-
Brailsford, A.D.1
Bullough, R.2
-
107
-
-
0001684276
-
Solute segregation in metals under irradiation
-
Johnson RA, Lam NQ. 1976. Solute segregation in metals under irradiation. Phys. Rev. B 13:4364-75
-
(1976)
Phys. Rev.B
, vol.13
, pp. 4364-4375
-
-
Johnson, R.A.1
Lam, N.Q.2
-
108
-
-
0142207970
-
Report on the CEA program of investigations of radiation-induced cavities in metals: Presentation of some results
-
ed. JW Corbett, LC Ianniello
-
Adda Y. 1972. Report on the CEA program of investigations of radiation-induced cavities in metals: presentation of some results. In Radiation-Induced Voids in Metals, ed. JW Corbett, LC Ianniello, pp. 31
-
(1972)
Radiation-Induced Voids in Metals
, pp. 31
-
-
Adda, Y.1
-
110
-
-
0016528417
-
The effects of cold working and pre-irradiation heat treatment on void formation in neutron-irradiated type 316 stainless steel
-
Brager HR. 1975. The effects of cold working and pre-irradiation heat treatment on void formation in neutron-irradiated type 316 stainless steel. J. Nucl. Mater. 57:103-18
-
(1975)
J. Nucl. Mater
, vol.57
, pp. 103-118
-
-
Brager, H.R.1
-
111
-
-
0020145467
-
Void-swelling and precipitation in a neutron-irradiated, niobium-stabilised austenitic stainless steel
-
Williams TM, Titchmarsh JM, Arkell DR. 1982. Void-swelling and precipitation in a neutron-irradiated, niobium-stabilised austenitic stainless steel. J. Nucl. Mater. 107:222-44
-
(1982)
J. Nucl. Mater
, vol.107
, pp. 222-244
-
-
Williams, T.M.1
Titchmarsh, J.M.2
Arkell, D.R.3
-
112
-
-
0026897697
-
Relationships between phase stability and void swelling in Fe-Cr-Ni alloys during irradiation
-
Lee EH, Mansur LK. 1992. Relationships between phase stability and void swelling in Fe-Cr-Ni alloys during irradiation. Metall. Trans. A 23:1977-86
-
(1992)
Metall. TransA
, vol.23
, pp. 1977-1986
-
-
Lee, E.H.1
Mansur, L.K.2
-
113
-
-
67349122668
-
Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT
-
McClintock DA, Sokolov MA, Hoelzer DT, Nanstad RK. 2009. Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT. J. Nucl. Mater. 392:353-59
-
(2009)
J. Nucl. Mater
, vol.392
, pp. 353-359
-
-
McClintock, D.A.1
Sokolov, M.A.2
Hoelzer, D.T.3
Nanstad, R.K.4
-
115
-
-
80053578285
-
Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325°C up to 78 dpa
-
Henry J, Averty X, Alamo A. 2011. Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325°C up to 78 dpa. J. Nucl. Mater. 417:99-103
-
(2011)
J. Nucl. Mater
, vol.417
, pp. 99-103
-
-
Henry, J.1
Averty, X.2
Alamo, A.3
-
116
-
-
0019079174
-
Helium trapping andTi-richMCparticles in neutron-irradiated type 316+Ti stainless steels
-
MaziaszPJ. 1980. Helium trapping andTi-richMCparticles in neutron-irradiated type 316+Ti stainless steels. Scr. Metall. 14:1251-56
-
(1980)
Scr. Metall
, vol.14
, pp. 1251-1256
-
-
Maziasz, P.J.1
-
117
-
-
0021820608
-
Apossible solution of the problem of helium embrittlement
-
Kesternich W.1985. Apossible solution of the problem of helium embrittlement. J. Nucl. Mater. 127:153-60
-
(1985)
J. Nucl. Mater
, vol.127
, pp. 153-160
-
-
Kesternich, W.1
-
118
-
-
0024035318
-
High temperature helium embrittlement in austenitic stainless steels-correlations between microstructure and mechanical properties
-
Schroeder H. 1988. High temperature helium embrittlement in austenitic stainless steels-correlations between microstructure and mechanical properties. J. Nucl. Mater. 155-157:1032-37
-
(1988)
J. Nucl. Mater
, vol.155-157
, pp. 1032-1037
-
-
Schroeder, H.1
-
119
-
-
0018727871
-
Simulation of first wall damage: Effects of the method of gas implantation
-
Packan NH, Farrell K. 1979. Simulation of first wall damage: effects of the method of gas implantation. J. Nucl. Mater. 85-86:677-81
-
(1979)
J. Nucl. Mater
, vol.85-86
, pp. 677-681
-
-
Packan, N.H.1
Farrell, K.2
-
120
-
-
0342356510
-
Swelling suppression in phosphorus-modified Fe-Cr-Ni alloys during neutron irradiation
-
14th, ed. NH Packan, RE Stoller, AS Kumar Philadelphia: Am. Soc. Test. Mater
-
Lee EH, Packan NH. 1989. Swelling suppression in phosphorus-modified Fe-Cr-Ni alloys during neutron irradiation. Int. Symp. Eff. Radiat. Mater., 14th, ed. NH Packan, RE Stoller, AS Kumar, pp. 133-46. Philadelphia: Am. Soc. Test. Mater.
-
(1989)
Int. Symp. Eff. Radiat. Mater
, pp. 133-146
-
-
Lee, E.H.1
Packan, N.H.2
-
121
-
-
0024035356
-
Microstructural development of austenitic stainless steels irradiated in HFIR
-
Tanaka MP, Hamada S, Hishinuma A, Maziasz PJ. 1988. Microstructural development of austenitic stainless steels irradiated in HFIR. J. Nucl. Mater. 155:801-5
-
(1988)
J. Nucl. Mater
, vol.155
, pp. 801-805
-
-
Tanaka, M.P.1
Hamada, S.2
Hishinuma, A.3
Maziasz, P.J.4
-
122
-
-
0027558428
-
Void swelling resistance of phosphorus-modified austenitic stainless steels during HFIR irradiation at 300-500°C to 57 dpa
-
Maziasz PJ. 1993. Void swelling resistance of phosphorus-modified austenitic stainless steels during HFIR irradiation at 300-500°C to 57 dpa. J. Nucl. Mater. 200:90-107
-
(1993)
J. Nucl. Mater
, vol.200
, pp. 90-107
-
-
Maziasz, P.J.1
-
123
-
-
0000267777
-
Defect and void evolution in oxide dispersion strengthened ferritic steels under 3.2MeV Fe+ ion irradiation with simultaneous helium injection
-
Kim I-S, Hunn JD, Hashimoto N, Larson DL, Maziasz PJ, et al. 2000. Defect and void evolution in oxide dispersion strengthened ferritic steels under 3.2MeV Fe+ ion irradiation with simultaneous helium injection. J. Nucl. Mater. 280:264-74
-
(2000)
J. Nucl. Mater
, vol.280
, pp. 264-274
-
-
Kim, I.-S.1
Hunn, J.D.2
Hashimoto, N.3
Larson, D.L.4
Maziasz, P.J.5
-
124
-
-
77956788208
-
Irradiation-tolerant nanostructured ferritic alloys: Transforming helium from a liability to an asset
-
Odette GR, Hoelzer DT. 2010. Irradiation-tolerant nanostructured ferritic alloys: transforming helium from a liability to an asset. JOM 62:84-92
-
(2010)
JOM
, vol.62
, pp. 84-92
-
-
Odette, G.R.1
Hoelzer, D.T.2
-
125
-
-
0016337538
-
Steady-state point-defect diffusion profiles in solids during irradiation
-
Lam NQ, Rothman SJ, Sizmann R. 1974. Steady-state point-defect diffusion profiles in solids during irradiation. Radiat. Effects 23:53-59
-
(1974)
Radiat. Effects
, vol.23
, pp. 53-59
-
-
Lam, N.Q.1
Rothman, S.J.2
Sizmann, R.3
-
126
-
-
0016046740
-
Calculated grain size-dependent vacancy supersaturation and its effect on void formation
-
Singh BN, Foreman AJE. 1974. Calculated grain size-dependent vacancy supersaturation and its effect on void formation. Philos. Mag. 29:847-57
-
(1974)
Philos. Mag
, vol.29
, pp. 847-857
-
-
Singh, B.N.1
Foreman, A.J.E.2
-
127
-
-
0018464748
-
Sink strengths for thin film surfaces and grain boundaries
-
Bullough R, Hayns MR, Wood MH. 1980. Sink strengths for thin film surfaces and grain boundaries. J. Nucl. Mater. 90:44-59
-
(1980)
J. Nucl. Mater
, vol.90
, pp. 44-59
-
-
Bullough, R.1
Hayns, M.R.2
Wood, M.H.3
-
128
-
-
30844458256
-
Microstructure of ion irradiated ceramic insulators
-
Zinkle SJ. 1994. Microstructure of ion irradiated ceramic insulators. Nucl. Instrum. Meth. Phys. Res. B 91:234-46
-
(1994)
Nucl. Instrum. Meth. Phys. Res.B
, vol.91
, pp. 234-246
-
-
Zinkle, S.J.1
-
129
-
-
78650648674
-
Atomic-scale design of radiation-tolerant nanocomposites
-
Demkowicz MJ, Bellon P, Wirth BD. 2010. Atomic-scale design of radiation-tolerant nanocomposites. MRS Bull. 35:992-98
-
(2010)
MRS Bull
, vol.35
, pp. 992-998
-
-
Demkowicz, M.J.1
Bellon, P.2
Wirth, B.D.3
-
130
-
-
51649148531
-
Unified theoretical analysis of experimental swelling data for irradiated austenitic and ferritic martensitic alloys
-
Lee EH, Mansur LK. 1990. Unified theoretical analysis of experimental swelling data for irradiated austenitic and ferritic martensitic alloys. Metall. Trans. A 21:1021-35
-
(1990)
Metall. TransA
, vol.21
, pp. 1021-1035
-
-
Lee, E.H.1
Mansur, L.K.2
-
131
-
-
43049167737
-
Theoretical basis for unified analysis of experimental data and design of swelling-resistant alloys
-
Mansur LK, Lee EH. 1991. Theoretical basis for unified analysis of experimental data and design of swelling-resistant alloys. J. Nucl. Mater. 179-181:105-10
-
(1991)
J. Nucl. Mater
, vol.179-181
, pp. 105-110
-
-
Mansur, L.K.1
Lee, E.H.2
-
132
-
-
59349115143
-
Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa
-
Edwards DJ, Garner FA, Bruemmer SM, Efsing P. 2009. Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa. J. Nucl. Mater. 384:249-55
-
(2009)
J. Nucl. Mater
, vol.384
, pp. 249-255
-
-
Edwards, D.J.1
Garner, F.A.2
Bruemmer, S.M.3
Efsing, P.4
-
133
-
-
79954453661
-
Helium transport, fate and management in nanostructured ferritic alloys: In situ helium implanter studies
-
Odette GR, Miao P, Edwards DJ, Yamamoto T, Kurtz RJ, Tanigawa H. 2011. Helium transport, fate and management in nanostructured ferritic alloys: in situ helium implanter studies. J. Nucl. Mater. 417:1001-4
-
(2011)
J. Nucl. Mater
, vol.417
, pp. 1001-1004
-
-
Odette, G.R.1
Miao, P.2
Edwards, D.J.3
Yamamoto, T.4
Kurtz, R.J.5
Tanigawa, H.6
-
134
-
-
0035560870
-
Theory and experiment of nanostructure self-organization in irradiated materials
-
Ghoniem NM, Walgraef D, Zinkle SJ. 2001. Theory and experiment of nanostructure self-organization in irradiated materials. J. Comp. Aided Mater. Des. 8:1-38
-
(2001)
J. Comp. Aided Mater. des
, vol.8
, pp. 1-38
-
-
Ghoniem, N.M.1
Walgraef, D.2
Zinkle, S.J.3
-
135
-
-
84863776201
-
Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750 degrees C in FFTF
-
Toloczko MB, Garner FA, Maloy SA. 2012. Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40-110 dpa at 400-750 degrees C in FFTF. J. Nucl. Mater. 428:170-75
-
(2012)
J. Nucl. Mater
, vol.428
, pp. 170-175
-
-
Toloczko, M.B.1
Garner, F.A.2
Maloy, S.A.3
-
136
-
-
84872158638
-
Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels
-
Certain A, Kuchibhatla S, Shutthanandan V, Hoelzer DT, Allen TR. 2013. Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels. J. Nucl. Mater. 434:311-21
-
(2013)
J. Nucl. Mater
, vol.434
, pp. 311-321
-
-
Certain, A.1
Kuchibhatla, S.2
Shutthanandan, V.3
Hoelzer, D.T.4
Allen, T.R.5
-
137
-
-
0030768918
-
Computational design of hierarchically structured materials
-
Olson GB. 1997. Computational design of hierarchically structured materials. Science 277:1237-42
-
(1997)
Science
, vol.277
, pp. 1237-1242
-
-
Olson, G.B.1
-
138
-
-
0036613788
-
THERMO-CALC & DICTRA, computational tools for materials science
-
Andersson JO, Helander T, Hoglund LH, Shi PF, Sundman B. 2002. THERMO-CALC & DICTRA, computational tools for materials science. CALPHAD 26:273-312
-
(2002)
CALPHAD
, vol.26
, pp. 273-312
-
-
Andersson, J.O.1
Helander, T.2
Hoglund, L.H.3
Shi, P.F.4
Sundman, B.5
-
139
-
-
84875458397
-
The high-throughput highway to computational materials design
-
Curtarolo S, Hart GLW, Nardelli MB, Mingo N, Sanvito S, Levy O. 2013. The high-throughput highway to computational materials design. Nat. Mater. 12:191-201
-
(2013)
Nat. Mater
, vol.12
, pp. 191-201
-
-
Curtarolo, S.1
Hart, G.L.W.2
Nardelli, M.B.3
Mingo, N.4
Sanvito, S.5
Levy, O.6
-
140
-
-
80955178912
-
Prospects for accelerated development of high performance structural materials
-
Zinkle SJ, Ghoniem NM. 2011. Prospects for accelerated development of high performance structural materials. J. Nucl. Mater. 417:2-8
-
(2011)
J. Nucl. Mater
, vol.417
, pp. 2-8
-
-
Zinkle, S.J.1
Ghoniem, N.M.2
-
141
-
-
84884904648
-
Effects of alloying elements and thermomechanical treatment on 9Cr reduced activation ferritic-martensitic (RAFM) steels
-
Tan L, Yang Y, Busby JT. 2013. Effects of alloying elements and thermomechanical treatment on 9Cr reduced activation ferritic-martensitic (RAFM) steels. J. Nucl. Mater. 442(Suppl.):13-17
-
(2013)
J. Nucl. Mater
, vol.442
, Issue.SUPPL.
, pp. 13-17
-
-
Tan, L.1
Yang, Y.2
Busby, J.T.3
-
142
-
-
84883404764
-
Challenges in developing materials for fusion technology-past, present, and future
-
Zinkle SJ. 2013. Challenges in developing materials for fusion technology-past, present, and future. Fusion Sci. Technol. 64:65-75
-
(2013)
Fusion Sci. Technol
, vol.64
, pp. 65-75
-
-
Zinkle, S.J.1
-
143
-
-
34248548644
-
Design of high-strength steels by microalloying and thermomechanical treatment
-
Barani AA, Li F, Romano P, Ponge D, Raabe D. 2007. Design of high-strength steels by microalloying and thermomechanical treatment. Mater. Sci. Eng. A 463:138-46
-
(2007)
Mater. Sci. EngA
, vol.463
, pp. 138-146
-
-
Barani, A.A.1
Li, F.2
Romano, P.3
Ponge, D.4
Raabe, D.5
-
144
-
-
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
-
146
-
-
84883318236
-
Frontiers in additive manufacturing: The shape of things to come
-
Lipson H. 2012. Frontiers in additive manufacturing: the shape of things to come. Bridge 42:5-12
-
(2012)
Bridge
, vol.42
, pp. 5-12
-
-
Lipson, H.1
-
147
-
-
0018047365
-
Deuterium trapping in irradiated 316 stainless steel
-
Wilson KL, Baskes MI. 1978. Deuterium trapping in irradiated 316 stainless steel. J. Nucl. Mater. 76- 77:291-97
-
(1978)
J. Nucl. Mater
, vol.76-77
, pp. 291-297
-
-
Wilson, K.L.1
Baskes, M.I.2
-
148
-
-
33748276464
-
Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids
-
Garner FA, Simonen EP, Oliver BM, Greenwood LR, Grossbeck ML, et al. 2006. Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids. J. Nucl. Mater. 356:122-35
-
(2006)
J. Nucl. Mater
, vol.356
, pp. 122-135
-
-
Garner, F.A.1
Simonen, E.P.2
Oliver, B.M.3
Greenwood, L.R.4
Grossbeck, M.L.5
-
149
-
-
67349227382
-
Recent analysis of key plasma wall interactions issues for ITER
-
Roth J, Tsitrone E, Loarte A, Loarer T, Counsell G, et al. 2009. Recent analysis of key plasma wall interactions issues for ITER. J. Nucl. Mater. 390-391:1-9
-
(2009)
J. Nucl. Mater
, vol.390-391
, pp. 1-9
-
-
Roth, J.1
Tsitrone, E.2
Loarte, A.3
Loarer, T.4
Counsell, G.5
-
150
-
-
84879899552
-
Deuterium retention in tungsten damaged withWions to various damage levels
-
Alimov VK, Hatano Y, Tyburska-Puschel B, Sugiyama K, Takagi I, et al. 2013. Deuterium retention in tungsten damaged withWions to various damage levels. J. Nucl. Mater. 441:280-85
-
(2013)
J. Nucl. Mater
, vol.441
, pp. 280-285
-
-
Alimov, V.K.1
Hatano, Y.2
Tyburska-Puschel, B.3
Sugiyama, K.4
Takagi, I.5
-
151
-
-
84893210439
-
Synergistic effects in hydrogen-helium bubbles
-
Hayward E, Deo C. 2012. Synergistic effects in hydrogen-helium bubbles. J. Phys. Condens. Matter 24:265402
-
(2012)
J. Phys. Condens. Matter
, vol.24
, pp. 265402
-
-
Hayward, E.1
Deo, C.2
-
152
-
-
84885469466
-
Molecular dynamics simulation of the effect of sub-surface helium bubbles on hydrogen retention in tungsten
-
Juslin N, Wirth BD. 2013. Molecular dynamics simulation of the effect of sub-surface helium bubbles on hydrogen retention in tungsten. J. Nucl. Mater. 438(Suppl.):1221-23
-
(2013)
J. Nucl. Mater
, vol.438
, Issue.SUPPL.
, pp. 1221-1223
-
-
Juslin, N.1
Wirth, B.D.2
-
153
-
-
58149307436
-
Tritium inventory in ITER plasmafacing materials and tritium removal procedures
-
Roth J, Tsitrone E, Loarer T, Philipps V, Brezinsek S, et al. 2008. Tritium inventory in ITER plasmafacing materials and tritium removal procedures. Plasma Phys. Control. Fusion 50:103001
-
(2008)
Plasma Phys. Control. Fusion
, vol.50
, pp. 103001
-
-
Roth, J.1
Tsitrone, E.2
Loarer, T.3
Philipps, V.4
Brezinsek, S.5
-
156
-
-
84884900386
-
A comparative TEM study of in-reactor and post-irradiation tensile tested copper
-
Pakarinen J, Tahtinen S, Singh BN. 2013. A comparative TEM study of in-reactor and post-irradiation tensile tested copper. J. Nucl. Mater. 442(Suppl.):821-25
-
(2013)
J. Nucl. Mater
, vol.442
, Issue.SUPPL.
, pp. 821-825
-
-
Pakarinen, J.1
Tahtinen, S.2
Singh, B.N.3
-
157
-
-
20644461913
-
Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy
-
Edwards DJ, Singh BN, Bilde-Sorensen JB. 2005. Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy. J. Nucl. Mater. 342:164-78
-
(2005)
J. Nucl. Mater
, vol.342
, pp. 164-178
-
-
Edwards, D.J.1
Singh, B.N.2
Bilde-Sorensen, J.B.3
-
158
-
-
70449520450
-
Design issues and implications for structural integrity of fusion power plant components
-
Karditsas PJ. 2009. Design issues and implications for structural integrity of fusion power plant components. Fusion Eng. Des. 84:2104-8
-
(2009)
Fusion Eng. des
, vol.84
, pp. 2104-2108
-
-
Karditsas, P.J.1
|