TY - GEN
T1 - Codes, standards, rules and assumptions on environment assisted fatigue for fatigue management of primary piping
AU - Solin, Jussi
AU - Seppänen, Tommi
AU - Vanninen, Rami
AU - Pulkkinen, Erkki
AU - Lemettinen, Petri
AU - Faidy, Claude
N1 - Funding Information:
This work is part of the FatiMa project ?Fatigue Management for LTO?, a sub-project of the Finnish Research Programme on Nuclear Power Plant Safety 2019-2022 (SAFIR2022). In addition to the generic Programme funding, Fortum and TVO provide also direct funds for execution of this project.
Publisher Copyright:
© 2020 ASME
PY - 2020/10/28
Y1 - 2020/10/28
N2 - All international codes used for design, operation and inspection of NPP primary circuit pressure boundaries are rooted to the ASME Boiler and Pressure Vessel Code, Section III, Nuclear Vessels, 1963. Article 4, N-415 “Analysis for cyclic operation” instructed calculation of stress intensities for fatigue transients and provided two design curves for basic material types. Different codes such as ASME, RCC-M, KTA, PNAE and JSME have much in common, but partial deviations exist. In 2007 the US NRC Regulatory Guide 1.207 endorsed a methodology for accounting the environmental effects. It was mainly based on extensive work in Japan and the Argonne National Laboratory. The final report of ANL, NUREG/CR-6909 became a major reference and subject of criticism. However, the first approach for environment assisted fatigue (EAF) written in 'code language' was published in Japan and a regulatory requirement for consideration of EAF both for operating reactors and new designs appeared first in Finland. This paper discusses challenges in management of fatigue and the evolving state-of-the-art in different codes, standards, rules and assumptions. The roots and current status of fatigue curves and design criteria applied in Finnish NPP's are explained.
AB - All international codes used for design, operation and inspection of NPP primary circuit pressure boundaries are rooted to the ASME Boiler and Pressure Vessel Code, Section III, Nuclear Vessels, 1963. Article 4, N-415 “Analysis for cyclic operation” instructed calculation of stress intensities for fatigue transients and provided two design curves for basic material types. Different codes such as ASME, RCC-M, KTA, PNAE and JSME have much in common, but partial deviations exist. In 2007 the US NRC Regulatory Guide 1.207 endorsed a methodology for accounting the environmental effects. It was mainly based on extensive work in Japan and the Argonne National Laboratory. The final report of ANL, NUREG/CR-6909 became a major reference and subject of criticism. However, the first approach for environment assisted fatigue (EAF) written in 'code language' was published in Japan and a regulatory requirement for consideration of EAF both for operating reactors and new designs appeared first in Finland. This paper discusses challenges in management of fatigue and the evolving state-of-the-art in different codes, standards, rules and assumptions. The roots and current status of fatigue curves and design criteria applied in Finnish NPP's are explained.
KW - Codes and standards
KW - EAF
KW - Fatigue
KW - Stainless steel
UR - http://www.scopus.com/inward/record.url?scp=85095865831&partnerID=8YFLogxK
U2 - 10.1115/PVP2020-21501
DO - 10.1115/PVP2020-21501
M3 - Conference article in proceedings
AN - SCOPUS:85095865831
VL - 1
T3 - American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
BT - ASME 2020 Pressure Vessels & Piping Conference
PB - American Society of Mechanical Engineers (ASME)
T2 - ASME 2020 Pressure Vessels and Piping Conference, PVP 2020
Y2 - 3 August 2020 through 3 August 2020
ER -