Overview of Reliability Test Program on Primary Coolant Piping of Light Water Reactors.

Shibata, Katsuyuki; Isozaki, Toshikuni; Ueda, Shuzo; Kurihara, Ryoichi; Onizawa, Kunio; Kosaka, Atsuo

doi:10.3327/jaesj.35.923

Cited by 3 publications

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“…Therefore, the set of Eqs. (2) and 3allows examination of the leak rate as a function of operation temperature and pressure, applied stress, crack size, and plate thickness. 2.…”

Section: Through Crack Leak and Flow Modelmentioning

confidence: 99%

“…Water leaks have been studied in the leak-before break (LBB) concept which is applied to assure structural safety of piping systems of light water reactors. 2) In this study, a leak rate on the order of 10 g/s was discussed, using twophase critical flow models. 3) However, for application to a tokamak machine, a much smaller leak of molecular flow must be considered as well as viscous flow.…”

Section: Introductionmentioning

confidence: 99%

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Structural Safety Assessment of a Tokamak-Type Fusion Facility for a Through Crack to Cause Cooling Water Leakage and Plasma Disruption

Nakahira

2004

J. Nucl. Sci. Technol.

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A tokamak-type fusion machine has inherent safety associated with plasma shutdown. A small water leak can cause a plasma disruption although there is another possibility to terminate plasma without disruption. This plasma disruption will induce electromagnetic (EM) forces acting in the vacuum vessel (VV). From a radiological safety viewpoint, the VV is designed to form a physical barrier that encloses tritium and activated dust. If the VV can sustain an unstable fracture by EM forces from a through crack to cause the small leak, the structural safety will be assured and the inherent safety will be demonstrated. Therefore, a systematic approach to assure the structural safety is developed. A new analytical model to evaluate the through crack and leak rate of cooling water is proposed, with verification by experimental leak measurements. Based on the analysis, the critical crack length to terminate plasma is evaluated as about 2 mm. On the other hand, the critical crack length for unstable fracture is obtained as about 400 mm. It is concluded that EM forces induced by the small leak to terminate plasma will not cause unstable fracture of the VV; thus the inherent safety is demonstrated.

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“…Therefore, the set of Eqs. (2) and 3allows examination of the leak rate as a function of operation temperature and pressure, applied stress, crack size, and plate thickness. 2.…”

Section: Through Crack Leak and Flow Modelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%