Influence of hydrogen on the toughness of irradiated reactor pressure vessel steels
Source abstract
Abstract
The influence of hydrogen on the mechanical behaviour of different reactor pressure vessel (RPV) steels was investigated by tensile tests in correlation to the chemical composition, the neutron fluence, the hydrogen charging condition, the strain rate, and the temperature. Small-angle neutron scattering (SANS) experiments, hydrogen analyses and thermal desorption investigations were performed to prove the evidence of hydrogen trapping at irradiation defects. An increasing susceptibility to hydrogen embrittlement indicated by reduction of area was observed at room temperature with in situ hydrogen-charged specimens when loaded by low strain rates or with specimens which had been irradiated at low temperature. Generally, the susceptibility increases with increasing strength of the steels. At 250 °C hydrogen embrittlement was not evident. The results do neither prove that irradiation defects are favoured traps for hydrogen nor give evidence that hydrogen affects the RPV integrity under normal operating conditions.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (32)
Show source-provided references
1. Hirth · Metall. Trans. · 1989 · 11A · 861
2. D. Pachur, in: Effects of radiation on materials: 18th International Symposium, Hyannis, MA, USA, June 22–25, 1996.
3. H. Hänninen, in: 20th meeting of AMES Steering Committee, Paris, March 2000, unpublished.
4. Splichal · J. Press. Vessel Piping · 1993 · 55 · 3361
5. Koutsky · Met. Mater. · 1985 · 23 · 252
6. C.R. Brinkman, J.M. Beeston, in: Irradiation effects on structural alloys for nuclear reactor applications, ASTM STP 484 (1970) 42.10.1520/STP26609S ↗
7. Takaku · J. Nucl. Mater. · 1982 · 110 · 28610.1016/0022-3115(82)90157-X ↗
8. Takaku · J. Nucl. Mater. · 1978 · 78 · 29910.1016/0022-3115(78)90451-8 ↗
9. Kimura · J. Nucl. Mater. · 1991 · 179–181 · 73710.1016/0022-3115(91)90194-C ↗
10. S.G. Lee, I.S. Kim, in: Proceedings of 11th International Conference on Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, August 10–14 (2003) 126.
11. Wu · J. Nucl. Mater. · 2004 · 328 · 11510.1016/j.jnucmat.2004.03.004 ↗
12. Wu · Corros. Sci. · 2005 · 47 · 141510.1016/j.corsci.2004.07.037 ↗
13. Wu · Mater. Corros. · 2005 · 56 · 30510.1002/maco.200403845 ↗
14. Krasikov · J. Nucl. Mater. · 2000 · 283–287 · 84610.1016/S0022-3115(00)00147-1 ↗
15. G. Brümmer, H. Hoffmann, F. Hütten, U. Ilg, O. Wachter, M. Widera, A. Brozova, J. Burda, O. Erben, M. Ernestova, J. Kysela, M. Postler, R. Vsolak, in: Proceedings of the 11th International Conference on Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, August 10–14 (2003) 116.
16. H.P. Seifert, S. Ritter, J. Hickling, in: Proceedings of the 11th International Conference on Environmental Degradation of Materials in Nuclear Systems, Stevenson, WA, August 10–14 (2003) 73.
17. G. Solt, F. Frisius, W.B. Weaber, P. Tipping, in: Effects of Radiation on Materials, ASTM STP 1175 (1993) 444.
18. Phytian · J. Nucl. Mater. · 1993 · 205 · 16210.1016/0022-3115(93)90079-E ↗
19. B.D. Wirth, G.R. Odette, P.A. Pavinich, G.E. Lucas, S.E. Spooner, in: Effects of Radiation on Materials, ASTM STP 1325 (1999) 102.
20. Ulbricht · Appl. Phys. A · 2002 · 74 · S112810.1007/s003390101203 ↗
21. Koester · Atom. Data Nucl. Data Tables. · 1991 · 49 · 6510.1016/0092-640X(91)90012-S ↗
22. Ulbricht · J. Nucl. Mater. · 2005 · 336 · 9010.1016/j.jnucmat.2004.09.005 ↗
23. M. Uhlemann, J. Böhmert, G. Müller, Einfluss von Wasserstoff auf die Zähigkeitsabnahme von RDB-Stählen, BMWA-Abschlussbericht IFW Dresden, 2001.
24. M. Uhlemann, G. Müller, A. Ulbricht, J. Böhmert, Einfluss von Wasserstoff auf die Zähigkeitsabnahme von bestrahlten RDB-Stählen, BMWA-Abschlussbericht IFW Dresden, 2004.
25. J. Böhmert, A. Gokhman, M. Große, A. Ulbricht, Nachweis, Interpretation und Bewertung bestrahlungsbedingter Gefügeänderungen in WWER-Reaktordruckbehälterstählen, Forschungszentrum Rossendorf, Wiss.-techn. Bericht FZR-381, 2003.
26. Müller · Praktische Metallographie · 2004 · 35 · 371
27. Kleiderling · Physica B · 1995 · 213&214 · 835
28. Wu · Mat. Sci. Eng. A · 2003 · 348 · 30910.1016/S0921-5093(02)00737-2 ↗
29. Brauer · Nucl. Eng. Design · 1991 · 127 · 4710.1016/0029-5493(91)90039-K ↗
30. Lee · Surface Coating Technol. · 1986 · 28 · 30110.1016/0257-8972(86)90087-3 ↗
31. Lee · Mat. Sci. Eng. A · 2006 · 420 · 27910.1016/j.msea.2006.01.080 ↗
32. Paroathavarthini · J. Nucl. Mater. · 2001 · 288 · 18710.1016/S0022-3115(00)00706-6 ↗