Published May 2002 | Version v1
Miscellaneous

P-T limit curve construction for the reactor pressure vessel : heatup curve

  • 1. KEPRI, Taejon (Korea, Republic of)

Description

During the startup and shutdown processes of the nuclear power plants, pressure and temperature are to be maintained below the P-T Limit Curve to prevent the non-ductile failure of the reactor pressure vessel. The ASME Sec. XI App. G describes the detailed procedure for constructing the P-T Limit Curve. Recently, several Code Cases as well as more accurate alternative methods were introduced to reduce the excess conservatism in App. G procedure. In this paper, for the startup, or heatup condition, the App. G procedure are reviewed. Then, the effects of the Code Cases on the P-T Limit Curves of the highly embrittled reactor pressure vessel are assessed. The results show that the current App. G procedure should be modified to consider the inner surface flaw under constant heatup rate when constructing the P-T Limit Curve for heatup condition. Also, when the Code Case N-588 is applied, the axial flaw in the less embrittled base metal has significant effect on the P-T Limit Curve in lower temperature range. Overall, the incorporation of the Code Cases greatly widens the allowable operating region during the heatup process

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS-KARP Joint spring meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[12 p.]

Conference

Title
2002 joint spring meeting of the KNS-KARP
Dates
23-24 May 2002
Place
Gwangju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34009796
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CODES; DIAGRAMS; DUCTILE-BRITTLE TRANSITIONS; NUCLEAR POWER PLANTS; PRESSURE DEPENDENCE; PRESSURE VESSELS; REACTOR VESSELS; TEMPERATURE DEPENDENCE
Descriptors DEC
CONTAINERS; INFORMATION; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Lead record
marp3-yh946
Notes
8 refs, 4 figs, 3 tabs