Lifetime and ageing management of nuclear power plants: A brief overview of some light water reactor component ageing degradation problems and ways of mitigation

International Journal of Pressure Vessels and Piping

Volumn 66, Issue 1-3, 1996, Pages 17-25

  Tipping, Philip ^a  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

Ageing mechanisms; Annealing; Environmentally assisted cracking; Mitigation measures; Neutron embrittlement; NPP life management; Pressure vessels; Steam generators; Water chemistry

Indexed keywords

AGING OF MATERIALS; AVAILABILITY; COMPONENTS; COOLING WATER; CORROSION; HIGH TEMPERATURE EFFECTS; IMPURITIES; LIGHT WATER REACTORS; NEUTRONS; NUCLEAR MATERIALS SAFEGUARDS; PLANT MANAGEMENT; THERMAL STRESS;

LIGHT WATER REACTOR COMPONENT; MITIGATION MEASURES; NEUTRON EMBRITTLEMENT; PLANT LIFE MANAGEMENT;

NUCLEAR POWER PLANTS;

EID: 0029732142     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/0308-0161(95)00082-8     Document Type: Article

References (16)

1. Odette, G.R., On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels. Script. Metall., 17(10), (1988), 1183-88.
2. Ghazi-Wakili, K., Tipping, Ph., Zimmermann, U. & Waeber, W., Investigation of neutron irradiated Fe-0.8%Cu alloys by means of positron annhilation and microhardness measurements. Zeitschrift für Phys. B, Cond. Mat., 79, (1990), 39-45.
3. Tipping, Ph., & Cripps, R., Annealing for Plant-life management: Hardness, tensile and Charpy toughness properties of irradiated, annealed and re-irradiated mock-up low alloy pressure vessel steel. Int. J. Pres. Ves. & Piping, 60, (1994), 217-222.
4. Proceedings of the DOE/SNL/EPRI Sponsored Reactor Pressure Vessel Thermal Annealing Workshop, February 17-18, (1994), Albuquerque, New Mexico, USA. SANDIA REPORT :SAND94-1515/2.UC-523. 1,2, (Issued in September 1994).
5. Hawthorne, J.R., Koziol, J.J. & Byrne, S.T., Evaluation of commercial production A533-B steel plates and weld deposits with extra low copper content for radiation resistance. In Effects of Radiation on Structural Materials, American Society for Testing and Materials, ASTM Special Technical Publication, ASTM-STP 683, ed. J. Sprague & D. Kramer. ASTM 1979, pp 235-51.
6. Hasegawa, M., Nakajima, N., Kusonoki, N. & Suzuki, K., Effects of copper and phosphorus on temper embrittlement of Mn-Mo-Ni low alloy steel (ASTM A533-B). Trans. Jap. Inst. Met., 16, (1975), 641-645.
7. Tipping, Ph., Isothermal annealing behaviour and Vickers Microhardness of irradiated mock-up pressure vessel weld material. In Proceedings of Third International Conference on Material science Problems in NPP Equipment production and Operation, Central Research Institute of Structural Materials "PROMETEY" in co-operation with IAEA, Moscow and St. Petersburg, 17-22 June, 1, (1994), 71-82.
8. Solt, G., Frisius, F., Waeber, W. & Tipping, Ph., Irradiation induced precipitation in model alloys with a systematic variation of Cu, Ni and P content: A small angle neutron scattering study. In Effects of Radiation Structural Materials: 16 th. International Symposium, American Society for Testing and Materials, ASTM Special Technical Publication, ASTM-STP 1175, ed. S. Arvind, S. Gelles, & R. Nanstad. ASTM 1993, 444-461.
9. Various authors in IAEA Specialists' Meeting on Steam Generator Problems and Replacement, Madrid, Spain, (1993), 13-16 December.
10. Jones, R., Gilman, J. & Nelson, L., Controlling stress corrosion cracking in Boiling Water Reactors. Nuclear Engineering & Design, 143, (1993), 111-123.
11. Slama, G., Mitigation of degradation processes in steam generators. In IAEA Specialists' Meeting on Steam Generator Problems and Replacement, Madrid, Spain, 13-16 December, (1993), 25-35.
12. Riccardella, P., Giannuzi, A. & Childs, W., Winning the battle against IGSCC. Nuc. Eng. Intl., June, (1992), 36-37.
13. Hickling, J. & Reizner, U., Water chemistry aspects of corrosion cracking taking BWR Plants as an example. VGB Kraftwerkstechnik 72, Nr. 4., (1992), 341-349.
14. BWR Hydrogen Water Chemistry Guidelines, 1987 Revision. EPRI Report NP-4947SR, Electric Power Research Institute, December, (1988).
15. Jacobs, A., Clausing, R., Miller, K & Shepherd, C., Influence of grain boundary composition on the IASCC susceptibility of Type 348 Stainless Steel. In Proceedings of 4 th. International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, National Association of Corrosion Engineers, (1990), 14/21-14/45.
16. Gordon, B., Hydrogen water chemistry for BWR. Task 27, Materials and Environmental Monitoring Within the Duane Arnold BWR, Contract RP1930-1, Electrical Power Research Institute.