Abstract
The Swedish reactor fleet consists of 7 BWRs and 3 PWRs which have been operating for up to 38 years and all have plans for long term operation (LTO).
The Swedish Radiation Safety Authority (SSM) has carried out an investigation to identify possible improvements to assessments for safe LTO. The study covered ageing mechanisms for metallic materials and polymers, concrete structures, electrical and I&C equipment, as well as in-service inspection. The paper will concentrate on metallic materials.
Most of the degradation mechanisms are controlled satisfactorily by the licensees through the existing inspection and ageing management programs. These should be intensified and reviewed with respect to LTO. The consequences of ageing degradation mechanisms for LTO should be analyzed and reported. Two ageing mechanisms are highlighted, low cycle fatigue in LWR environments and the embrittlement of RPV steels. However, analyses should be carried out for most of the ageing mechanisms to find early indications of degradation and thus ensure safety.
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References
“Swedish Radiation Safety Authority regulations concerning safety in nuclear facilities” (Regulation SSMFS 2008:1, Swedish Radiation Safety Authority, October 2008, in Swedish)
“Swedish Nuclear Power Inspectorate regulations concerning safety in nuclear facilities” (Regulation SKIFS 2004:1, Swedish Nuclear Power Inspectorate, June 2004, in Swedish)
“Safe Long Term Operation of Nuclear Power Plants”, Safety Report Series No. 57, IAEA, 2008.
B. Brickstad et al., “Supervision and requirements for long term operation of ageing nuclear power plants” (Report SSM 2010/659, Swedish Radiation Safety Authority, 2010)
“Swedish Radiation Safety Authority regulations concerning mechanical components in some nuclear facilities” (Regulation SSMFS 2008:13, Swedish Radiation Safety Authority, December 2008, in Swedish).
“Regulations of the pressure vessel safety in nuclear installations and facilities for storage of spent nuclear fuel” (Regulation SKI-FTKA, Swedish Nuclear Power Inspectorate, 1988, in Swedish).
“Radiation Embrittlement of Reactor Vessel Materials” (USNRC Regulatory Guide 1.99, Rev. 2, May 1988).
10CFR50app. G
P. Efsing, et al., “Analysis of the DBTT Shift in a Commercial Power Plant with High Nickel Containing Weld Material”, Journal of ASTM international, Vol. 4, No. 7, Aug. 2007.
IAEA Technical Meeting on Irradiation Embrittlement and Life Management of Reactor Pressure Vessels (RPV) in NPPs, 18–22 October 2010, Znojmo, Czech Republic, http://www.iaea.org/NuclearPower/Engineering/Meetings/2010-10-TM-Czech.html
M.A. Kirk, “Wide-Range Embrittlement Trend Curves for Western RPV Steels” (Presented at the Fontevraud 7 Symposium Contributions of Materials Investigations to Improve the Safety and Performance of LWRs, 26–30 September 2010).
K. Asano et al., “Current Understanding on the Neutron Irradiation Embrittlement of BWR Reactor Pressure Vessel Steels in Japan” (Presented at the Fontevraud 7 Symposium Contributions of Materials Investigations to Improve the Safety and Performance of LWRs, 26–30 September 2010).
A-S. Bogaert et al., “Comparison of embrittlement trend curves to high fluence surveillance results” (Presented at the Fontevraud 7 Symposium Contributions of Materials Investigations to Improve the Safety and Performance of LWRs, 26–30 September 2010)
ASME Boiler & Pressure Vessel Code, ASME III, Division 1, NB-3000, 2007.
“Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components” (SSM Research Report 2011:04, Swedish Radiation Safety Authority, January 2011).
K. Steingrimsdottir, “Fatigue Analysis Including Environmental Effects for a Pipe System in a Swedish BWR” (Report No. 50009450-4, Rev. 4, Inspecta Technology AB, 2010-10-15).
O.K. Chopra and W.J. Shack, “Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials”, NUREG/CR-6909, USNRC, February 2007.
J. Wåle, “Effect of Thermal Ageing on the Mechanical Properties of Cast Stainless Steel — A Literature Review” (SKI-projekt 13.2-0879/90, SA/FoU-Rapport 90/10.
C. Jansson, “Degradation of Cast Stainless Steel Elbows after 15 Years in Service”(Presented at the Fontevraud II, International Symposium, 10–14 September 1990).
TBM, Technical requirements for mechanical components. Issue 5, 2008-03-06.
K. Gott, “Databases of Operationally Induced Damage” (Presented at the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, Colorado Spring, August 7–11, 2011).
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© 2011 TMS (The Minerals, Metals & Materials Society)
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Ekström, P., Gott, K., Brickstad, B. (2011). Conditions for Long Term Operation of Nuclear Power Plants in Sweden. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_2
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DOI: https://doi.org/10.1007/978-3-319-48760-1_2
Publisher Name: Springer, Cham
Online ISBN: 978-3-319-48760-1
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