Influence of manganese on mechanical properties, irradiation susceptibility and microstructure of ferritic steels, alloys and welds
Source abstract
Abstract
The ferritic steels used world wide for nuclear pressure vessels and irradiated structures contain manganese but knowledge of the role of manganese is mainly confined to the unirradiated condition. Information from the mid 1950s to 2009 on the influence of manganese on unirradiated and irradiated properties is analysed. In unirradiated material manganese raises ambient strength, improves notched impact toughness, benefits high temperature strength, promotes dynamic strain aging and enhances creep resistance. However, by combining with carbon and by increasing phosphorus diffusion, manganese increases intergranular embrittlement after thermal aging. Neutron irradiated steels are deleteriously affected by manganese. First, the dose coefficients of irradiation hardening and embrittlement increase linearly with manganese, particularly in steels with uncombined nitrogen, and the morphology of irradiation induced interstitial loops is altered. Second, manganese occurs in irradiation induced Cu rich precipitates, altering their morphology and the associated hardening. Third, manganese becomes incorporated into irradiation enhanced Cu–Ni–Mn precipitates and Mn–Ni–Si nanoclusters that increase hardening and embrittlement at high doses. Finally, manganese segregates at grain boundaries under irradiation. Overall, the unirradiated benefits are outweighed by deleterious irradiation effects. These factors are important in supporting continued reactor operations, extending lifetimes of existing nuclear vessels and structures, improving steel specifications for advanced reactors and developing steels for nuclear fusion applications.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (100+)
Show source-provided references
1. 10.4028/www.scientific.net/MSF.46.6110.4028/www.scientific.net/MSF.46.61 ↗
2. 10.1520/STP23038S10.1520/STP23038S ↗
3. 10.1520/STP12402S10.1520/STP12402S ↗
4. Proc. Workshop on ‘Dose rate effects in RPV materials’, Squaw Creek, CA, USA, November 2001, EPRI and CRIEPI.
5. 10.1520/STP16495S10.1520/STP16495S ↗
6. 10.1098/rsta.1985.004210.1098/rsta.1985.0042 ↗
7. 10.1520/STP41325S10.1520/STP41325S ↗
8. 10.1016/S1359-6454(02)00277-X10.1016/S1359-6454(02)00277-X ↗
9. Odette GR, Lucas GE:in‘The effects of radiation on materials: 14th international symposium’(, Packan N H, et al.), ASTM STP 1046, Vol. 2, 323; 1990, Philadelphia, PA, ASTM.
10. Jones RB, Buswell JT: Proc. 3rd Int. Symp. on ‘Environmental degradation of materials in nuclear power systems-water reactors’, (ed. G. J. Theus and W. Berry), 111–120; 1988, Traverse City, MI, TMS.
11. Pickering FB: ‘Physical metallurgy and the design of steels’, Materials science series; 1970, London, Applied Science Publishers Ltd.
12. Baird JD · J. Iron Steel Inst. · 1966 · 793
13. Alekseenko NN, Amaev A, Gorynin I, Nikolaev VA: ‘Radiation damage of nuclear power plant pressure vessel steels’, Russian materials monograph series; 1997, La Grange Park, IL, American Nuclear Society.
14. Hopkin LMT · J. Iron Steel Inst. · 1965 · 583
15. Ishida Y · J. Iron Steel Inst. · 1967 · 83
16. Allen NP · J. Iron Steel Inst. · 1953 · 108
17. 10.1007/BF0264857110.1007/BF02648571 ↗
18. 10.1016/0036-9748(87)90108-610.1016/0036-9748(87)90108-6 ↗
19. 10.1007/BF0267727510.1007/BF02677275 ↗
20. Watanabe J, Shindo J, Murakami J, Adachi T, Ajiki S, Miyar K: Proc. ASME 29th Petroleum Mechanical Engineering Conf., Dallas, TX, USA, September 1974, ASME.
21. Viswanathan R, Gehl S: Proc. Robert I Jaffee Memorial Symp. on ‘Clean materials technology’, Chicago, IL, USA, November 1992, ASM, 59–67.
22. Friedman LM: Proc. Robert I Jaffee Memorial Symp. on ‘Clean materials technology’, Chicago, IL, USA, November 1992, ASM, 77–80.
23. Jones RB, Bolton CJ: Proc. 24th Water Reactor Safety Information Meet., Bethesda, MD, USA, October 1996, USNRC, NUREG/CP-0157, 1997, Vol. 2, 25–48.
24. Fidler RS, Bolton CJ, Beere WB, Fenton ST, Jones RB: Nuclear Electric internal document , 1994.
25. 10.1520/STP13866S10.1520/STP13866S ↗
26. Walmsley JC, Corcoran R, Spellward P, Fenton ST: ‘Nanochemical characterisation of nuclear plant materials’, Proc. Microstructural Conf., Cambridge, UK, September 1996, Cambridge University
27. Phythian WJ, de Diego N, Mace J, McElroy RJ:in‘Effects of radiation on materials: 16th international symposium’(, Kumar A S, et al.), ASTM STP 1175, 462–491; 1994, Philadelphia, PA, ASTM.10.1520/STP23952S ↗
28. Little EA · Int. Metall. Rev. · 1976 · 25
29. 10.1016/0308-0161(87)90007-X10.1016/0308-0161(87)90007-X ↗
30. Buswell JT, Jones RB:in‘Effects of radiation on materials: 16th international symposium’(, Kumar A S, et al.), 424–443; 1994, Philadelphia, PA, ASTM.10.1520/STP23950S ↗
31. Barton PJ · J. Iron Steel Inst. · 1965 · 203 · 501
32. Jones RB, Buswell JT, Wootton MR: Proc. EPRI/CRIEPI Workshop on ‘Dose rate effects in RPV materials’, Squaw Creek, CA, USA, November 2001, EPRI/CRIEPI, Paper 9.
33. 10.1080/1478643600823583910.1080/14786436008235839 ↗
34. 10.1016/0001-6160(60)90200-510.1016/0001-6160(60)90200-5 ↗
35. Odette GR:‘Microstructural evolution during irradiation’Proc. Materials Research Society Symp.(, Robertson I M, et al.), Vol. 373, 137–148; 1995, Warrendale, PA, Materials Research Society.
36. Jones RB: Proc. IAEA Meet. on ‘Irradiation effects and mitigation in reactor pressure vessel and reactor internals’, Gus Khrustalny, Russia, May 2004, IAEA. Available in ‘Embrittlement and mechanistic interpretation of reactor pressure vessel and internal materials, publ. European Commission, JRC Petten, The Netherlands, EUR 21835, 2005, 102–121.
37. 10.1520/STP16470S10.1520/STP16470S ↗
38. ‘Standard practice for characterising neutron exposures in terms of displacements-per-atom’, E693-79, ASTM, West Conshohocken, PA, USA, 1985
39. 10.1016/0022-3115(95)00022-410.1016/0022-3115(95)00022-4 ↗
40. 10.1520/STP12414S10.1520/STP12414S ↗
41. 10.1520/STP12404S10.1520/STP12404S ↗
42. Badanin VI · Voprozy Sudostr. Ser. Metall. · 1975 · 92
43. Takeyama T · Trans. JISI · 1981 · 21 · 326
44. Nikolaev V, Rybin VV:in‘Effects of radiation on materials: 17th international symposium’(, Gelles D S, et al.), ASTM STP 1270, 9–24; 1996, West Conshohocken, PA, ASTM.
45. 10.1520/STP16494S10.1520/STP16494S ↗
46. Chivers KF, Huntingdon S, Odette GR: Proc. IGRDM-11, San Diego, CA, USA, September 2003, IGRDM.
47. Odette GR, Lucas GE, Klingensmith RD, Wirth BD, Gragg D: ‘The effect of composition and heat treatment on hardening and embrittlement of reactor pressure vessel steels’, NUREG/CR-6778, US Nuclear Regulatory Commission, Washington DC, USA, 2003.
48. 10.1080/0267837041233132005310.1080/02678370412331320053 ↗
49. 10.1080/1478643041233131991010.1080/14786430412331319910 ↗
50. Grounes M: ‘Irradiation effects in 2103/R3 steel – comparison between different heats and different fabrication procedures’, Report S386, Aktiebolaget Atomenergi, Studsvik, Nykoping, Sweden, 1968.10.13182/NT68-A28024 ↗
51. Nichols RW, Harries DR: in ‘Radiation effects on metals and neutron dosimetry’, ASTM STP 341, 162–198; 1962, Philadelphia, PA, ASTM; also published in Proc. ANS Annual Meeting, Canada, 1968.
52. Jones RB: ‘Influence of neutron spectrum on the hardening of iron, steels and welds’, Proc. IGRDM-10, Awaji Island, Japan, May 2002, IGRDM.
53. Miles L: ‘Correlation between site-determined hardness and yield strength’, Nuclear electric memorandum TD/SIP/MEM/1109/92, Nuclear Electric, Bristol, UK, 1992.
54. Jones RB: Unpublished database of hardness and tensile data for weld metals.
55. 10.1179/msc.1970.4.1.18810.1179/msc.1970.4.1.188 ↗
56. 10.1179/msc.1970.4.1.19510.1179/msc.1970.4.1.195 ↗
57. Eason ED, Wright JE, Odette GR: ‘Improved embrittlement correlations for reactor pressure vessel steels’, NUREG/CR-6551, US Nuclear Regulatory Commission, Washington DC, USA, 1998.10.1016/S0029-5493(97)00286-0 ↗
58. ‘Charpy embrittlement correlations – status of combined mechanistic and statistical bases for US RPV steels’, EPRI report MRP-45, EPRI, Palo Alto, CA, USA, 2001
59. 10.1520/STP17859S10.1520/STP17859S ↗
60. Langer R, Bartsch R, Fohl J: Proc. EPRI/CRIEPI Workshop on ‘Dose rate effects in reactor pressure vessel materials’, Squaw Creek, CA, USA, November 2001, EPRI/CRIEPI, Paper 15.
61. Debarberis L, Ballesteros A: Proc. IAEA Meet. on ‘Irradiation effects and mitigation in reactor pressure vessel and reactor internals’, Gus Khrustalny, Russia, May 2004, IAEA. Available in ‘Embrittlement and mechanistic interpretation of reactor pressure vessel and internal materials, publ. European Commission, JRC Petten, The Netherlands, EUR 21835, 2005, 54–62.
62. 10.1520/STP23038S10.1520/STP23038S ↗
63. 10.1520/STP34358S10.1520/STP34358S ↗
64. Pachur D, Sievers G: ‘Irradiation programme for pressure vessel steels’, Julich, KFA, 1974.
65. Hawthorne JR, Menke BH, Hiser AL: in ‘Effects of radiation on materials: 12th international symposium’, (ed. , Garner F A, Perrin J S, ed), ASTM STP 870, 1163; 1985, Philadelphia, PA, ASTM.10.1520/STP87019850037 ↗
66. 10.1080/1042015980822967610.1080/10420159808229676 ↗
67. Stofanak RJ, Poskie TJ, Liu YY, Wire GL: Proc. 6th Int. Symp. on ‘Environmental degradation of materials in nuclear power systems: water reactors’, (ed. , Gold R E, Simonen E P, ed), 757–763; 1993, Warrendale, PA, TMS.
68. Burke MG, Stofanak RJ, Hyde JM, English CA, Server WA: Proc. EPRI/CRIEPI Workshop on ‘Dose rate effects in reactor pressure vessel materials’, Squaw Creek, CA, USA, November 2001, EPRI/CRIEPI, Paper 13.
69. Burke MG, Stofanak RJ, Hyde JM, English CA, Server WA:in‘Effects of radiation on materials: 21st international symposium’(, Grossbeck M L, et al.), ASTM STP 1447, 194–207; 2002, Philadelphia, PA, ASTM.
70. Burke MG, Stofanak RJ, Hyde JM, English CA, Server WA: Proc. 10th Int. Symp. on ‘Environmental degradation of materials in nuclear power systems: water reactors’, (ed. , Was G, Nelson L, ed) Lake Tahoe, NV, USA, 2002, NACE.
71. 10.1007/s10853-006-0084-x10.1007/s10853-006-0084-x ↗
72. Badanin VI · Phys. Met. Metallogr. · 1979 · 21
73. Nikolaev VA · Atomnaya Energ. · 1974 · 37 · 491
74. Nikolaev VA · Atomnaya Energ. · 1984 · 57 · 167
75. 10.1520/STP26617S10.1520/STP26617S ↗
76. 10.1115/1.342825510.1115/1.3428255 ↗
77. Hawthorne JR, Watson HE: in ‘Properties of reactor structural alloys after neutron or particle irradiation’, (ed. , Baroch C J, ed), ASTM STP 570, 54–71; 1975, Philadelphia, PA, ASTM.
78. Nishiyama Y, Fukaya K, Suzuki M, Ito M: ‘Irradiation embrittlement of 2·25Cr–1Mo steel at 400 °C’, Research report 97-039, JAERI, Ibaraki, Japan, 1997.
79. ‘Integrity of reactor pressure vessels in nuclear power plants: assessment of irradiation embrittlement effects in reactor pressure vessel steels’, Technical report NP-T-3·11, IAEA, Vienna, Austria, 2009.
80. 10.1016/j.jnucmat.2009.01.29910.1016/j.jnucmat.2009.01.299 ↗
81. Nikolaev YuA, Nikolaeva AV, Shtrombakh YaI: Proc. IAEA Specialists Meet. on ‘Radiation effects and mitigation’, Gloucester, UK, May 2001, IAEA, 131–154.
82. Nikolaev YuA · J. ASTM Int. · 2007 · 4
83. 10.1016/0022-3115(95)00097-610.1016/0022-3115(95)00097-6 ↗
84. 10.1016/S0308-0161(02)00069-810.1016/S0308-0161(02)00069-8 ↗
85. Debarberis L, Acosta B, Sevini F: ‘State of the art on the role of nickel and manganese on radiation embrittlement’, EUR 21304 EN, European Commission, Petten, The Nertherland, 2004.
86. 10.1016/S0308-0161(02)00068-610.1016/S0308-0161(02)00068-6 ↗
87. 10.1080/0033757720823468910.1080/00337577208234689 ↗
88. 10.4028/www.scientific.net/MSF.654-656.291110.4028/www.scientific.net/MSF.654-656.2911 ↗
89. 10.1016/0022-3115(82)90490-110.1016/0022-3115(82)90490-1 ↗
90. Nicol AC, Jenkins ML, Kirk MA:Proc. 2000 Materials Research Society Symp.(, Lucas G E, et al.), R1, 3·1–3·6; 2001, Warrendale, PA, Materials Research Society.
91. Ibrahimi DT:‘Microstructure of irradiated materials’Proc. 1994 Materials Research Society Symp.(, Robertson I M, et al.), 57; 1995, Warrendale, PA, Materials Research Society.
92. Buswell JT: ‘Analysis of the behaviour of advanced reactor pressure vessel steels under neutron irradiation: the UK programme’, UK Report for the IAEA co-ordinated research programme on the behaviour of advanced reactor pressure vessel steels under neutron irradiation, Annex 9, UKAEA, Chilton, UK, 1983, 281–315.
93. 10.1016/0022-3115(93)90082-A10.1016/0022-3115(93)90082-A ↗
94. 10.1520/STP13909S10.1520/STP13909S ↗
95. 10.1016/0022-3115(90)90017-H10.1016/0022-3115(90)90017-H ↗
96. 10.1520/STP12401S10.1520/STP12401S ↗
97. 10.1016/S0022-3115(02)00800-010.1016/S0022-3115(02)00800-0 ↗
98. 10.1016/S0022-3115(98)00455-310.1016/S0022-3115(98)00455-3 ↗
99. 10.1016/S0022-3115(00)00007-610.1016/S0022-3115(00)00007-6 ↗
100. 10.1016/0022-3115(87)90525-310.1016/0022-3115(87)90525-3 ↗