Published October 2012 | Version v1
Miscellaneous

Evaluation of fatigue damage induced by thermal striping in a T junction using the three dimensional coupling method and frequency response method

  • 1. Sungkyunkwan Univ., Seoul (Korea, Republic of)
  • 2. Seoul Nat'l Univ., Seoul (Korea, Republic of)
  • 3. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

Thermal fatigue cracking induced by thermal stratification, cycling and striping have been observed in several PWR plants. Especially, thermal striping, the highly fluctuating thermal layer, became one of the significant problems, since it can cause un predicted high cycle thermal fatigue (HCTF) at piping systems. This problem are usually found in T junctions of energy cooling systems, where cold and hot flows with high level of turbulence mix together. Thermal striping can cause the networks of fatigue crack at the vicinity of weld parts and these cracks can propagate to significant depth in a relatively short time. Therefore, thermal striping and fatigue crack initiations should be predicted in advance to prevent the severe failure of piping systems. The final goal of this research is to develop a rational thermal and mechanical model considering thermohydraulic characteristics of thermal striping and an evaluation procedure to predict the initiation of thermal fatigue crack. As a first step, we evaluated the fatigue damage in a T junction using two widely used methods. Then, we analyzed the results of each method and conducted comparisons and verifications

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2012 autumn meeting of the KNS
Dates
24-26 Oct 2012
Place
Kyoungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44062789
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CRACKING; CRACKS; DAMAGE; EVALUATION; FATIGUE; PWR TYPE REACTORS; STRATIFICATION; VERIFICATION
Descriptors DEC
CHEMICAL REACTIONS; DECOMPOSITION; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PYROLYSIS; REACTORS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs, 5 figs, 1 tab