NB-3650M fatigue calculation procedure

Paul Smeekes, Eero Torkkeli, Mårten Perklen, Otso Cronvall

Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

Abstract

Fatigue is considered a significant long-term degradation mechanism for safety significant pressure equipment in nuclear power plants. The ASME Section III [1] procedure aims to prevent formation of fatigue cracks during the specified service period. Practical experience gathered during tens of years with hundreds of reactors has shown that the ASME methodology functions very well or is even conservative. Several studies performed in the USA and Japan indicated significant environmental effects on the fatigue as compared to fatigue without environmental effects. This has yielded a methodology as described in the NUREG/CR-6909 [2] and the JSME S NF1-2006 [17]. This methodology should obviously be applied on a best estimate fatigue analysis with reasonable safety factors. Due to the fact that such an analysis is not available and as the ASME methodology functions well this methodology is applied in conjunction with the ASME methodology. Obviously this is conservative, possibly even far overconservative. From an analytical point of view the NB3600 (engineering approach) and NB3200 (detailed 3D analysis) fatigue analysis methodology and the one in the NUREG/CR-6909 (full time history) are not compatible. In the work presented here a methodology was developed to combine these methods.
Original languageEnglish
Title of host publicationBaltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts
EditorsPertti Auerkari, Juha Veivo
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages22
ISBN (Electronic)978-951-38-8030-9
ISBN (Print)978-951-38-8029-3
Publication statusPublished - 2013
MoE publication typeNot Eligible
EventBALTICA IX - International Conference on Life Management and Maintenance for Power Plants - Helsinki-Stockholm, Finland
Duration: 11 Jun 201313 Jun 2013

Publication series

NameVTT Technology
PublisherVTT
Number107
ISSN (Print)2242-1211
ISSN (Electronic)2242-122X

Conference

ConferenceBALTICA IX - International Conference on Life Management and Maintenance for Power Plants
CountryFinland
CityHelsinki-Stockholm
Period11/06/1313/06/13

Fingerprint

Fatigue of materials
Environmental impact
Safety factor
Nuclear power plants
Degradation

Cite this

Smeekes, P., Torkkeli, E., Perklen, M., & Cronvall, O. (2013). NB-3650M fatigue calculation procedure. In P. Auerkari, & J. Veivo (Eds.), Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts (pp. 22). Espoo: VTT Technical Research Centre of Finland. VTT Technology, No. 107
Smeekes, Paul ; Torkkeli, Eero ; Perklen, Mårten ; Cronvall, Otso. / NB-3650M fatigue calculation procedure. Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. editor / Pertti Auerkari ; Juha Veivo. Espoo : VTT Technical Research Centre of Finland, 2013. pp. 22 (VTT Technology; No. 107).
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Smeekes, P, Torkkeli, E, Perklen, M & Cronvall, O 2013, NB-3650M fatigue calculation procedure. in P Auerkari & J Veivo (eds), Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. VTT Technical Research Centre of Finland, Espoo, VTT Technology, no. 107, pp. 22, BALTICA IX - International Conference on Life Management and Maintenance for Power Plants, Helsinki-Stockholm, Finland, 11/06/13.

NB-3650M fatigue calculation procedure. / Smeekes, Paul; Torkkeli, Eero; Perklen, Mårten; Cronvall, Otso.

Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. ed. / Pertti Auerkari; Juha Veivo. Espoo : VTT Technical Research Centre of Finland, 2013. p. 22 (VTT Technology; No. 107).

Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

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AU - Torkkeli, Eero

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PY - 2013

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N2 - Fatigue is considered a significant long-term degradation mechanism for safety significant pressure equipment in nuclear power plants. The ASME Section III [1] procedure aims to prevent formation of fatigue cracks during the specified service period. Practical experience gathered during tens of years with hundreds of reactors has shown that the ASME methodology functions very well or is even conservative. Several studies performed in the USA and Japan indicated significant environmental effects on the fatigue as compared to fatigue without environmental effects. This has yielded a methodology as described in the NUREG/CR-6909 [2] and the JSME S NF1-2006 [17]. This methodology should obviously be applied on a best estimate fatigue analysis with reasonable safety factors. Due to the fact that such an analysis is not available and as the ASME methodology functions well this methodology is applied in conjunction with the ASME methodology. Obviously this is conservative, possibly even far overconservative. From an analytical point of view the NB3600 (engineering approach) and NB3200 (detailed 3D analysis) fatigue analysis methodology and the one in the NUREG/CR-6909 (full time history) are not compatible. In the work presented here a methodology was developed to combine these methods.

AB - Fatigue is considered a significant long-term degradation mechanism for safety significant pressure equipment in nuclear power plants. The ASME Section III [1] procedure aims to prevent formation of fatigue cracks during the specified service period. Practical experience gathered during tens of years with hundreds of reactors has shown that the ASME methodology functions very well or is even conservative. Several studies performed in the USA and Japan indicated significant environmental effects on the fatigue as compared to fatigue without environmental effects. This has yielded a methodology as described in the NUREG/CR-6909 [2] and the JSME S NF1-2006 [17]. This methodology should obviously be applied on a best estimate fatigue analysis with reasonable safety factors. Due to the fact that such an analysis is not available and as the ASME methodology functions well this methodology is applied in conjunction with the ASME methodology. Obviously this is conservative, possibly even far overconservative. From an analytical point of view the NB3600 (engineering approach) and NB3200 (detailed 3D analysis) fatigue analysis methodology and the one in the NUREG/CR-6909 (full time history) are not compatible. In the work presented here a methodology was developed to combine these methods.

M3 - Conference abstract in proceedings

SN - 978-951-38-8029-3

T3 - VTT Technology

SP - 22

BT - Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts

A2 - Auerkari, Pertti

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Smeekes P, Torkkeli E, Perklen M, Cronvall O. NB-3650M fatigue calculation procedure. In Auerkari P, Veivo J, editors, Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. Espoo: VTT Technical Research Centre of Finland. 2013. p. 22. (VTT Technology; No. 107).