Improvement of predictive capability of environmentally assisted cracking by means of computer simulation of crack propagation

Tetsuo Shoji; S. Moriya; H. Arai; M. Higashi

Improvement of predictive capability of environmentally assisted cracking by means of computer simulation of crack propagation

Tetsuo Shoji, S. Moriya, H. Arai, M. Higashi

New Industry Creation Hatchery Center (NICHe)

Research output: Contribution to journal › Conference article › peer-review

3 Citations (Scopus)

Abstract

It is of practical importance to predict the stress corrosion crack (SCC) crack growth behavior in the pressure boundary components of nuclear power plants during operation. The establishment of the prediction method of SCC initiation and growth in light water reactor (LWR) environment is one of the essential steps in structural integrity assessment. In this paper, based upon a dissolution model, crack growth behavior of stress corrosion cracking of reactor pressure vessel steel of SA533B in simulated LWR environment under monotonic rising load (in other words Slow Strain Rate Test) and constant loading was simulated by the combination of FEM stress-strain analysis on growing crack and dissolution model. From the simulation results, the relationship between crack tip strain rate and crack propagation rate was discussed quantitatively. Crack growth rate can be evaluated in terms of both the crack tip strain rate and the crack tip solution chemistry such as, sulfur concentration and steady state dissolution rate (I_SS).

Original language	English
Pages (from-to)	107-113
Number of pages	7
Journal	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	287
Publication status	Published - 1994 Dec 1
Event	Proceedings of the 1994 Pressure Vessels and Piping Conference. Part 2 (of 19) - Minneapolis, MN, USA Duration: 1994 Jun 19 → 1994 Jun 23

ASJC Scopus subject areas

Mechanical Engineering

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Improvement of predictive capability of environmentally assisted cracking by means of computer simulation of crack propagation. / Shoji, Tetsuo; Moriya, S.; Arai, H.; Higashi, M.

In: American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, Vol. 287, 01.12.1994, p. 107-113.

Research output: Contribution to journal › Conference article › peer-review

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abstract = "It is of practical importance to predict the stress corrosion crack (SCC) crack growth behavior in the pressure boundary components of nuclear power plants during operation. The establishment of the prediction method of SCC initiation and growth in light water reactor (LWR) environment is one of the essential steps in structural integrity assessment. In this paper, based upon a dissolution model, crack growth behavior of stress corrosion cracking of reactor pressure vessel steel of SA533B in simulated LWR environment under monotonic rising load (in other words Slow Strain Rate Test) and constant loading was simulated by the combination of FEM stress-strain analysis on growing crack and dissolution model. From the simulation results, the relationship between crack tip strain rate and crack propagation rate was discussed quantitatively. Crack growth rate can be evaluated in terms of both the crack tip strain rate and the crack tip solution chemistry such as, sulfur concentration and steady state dissolution rate (ISS).",

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AU - Shoji, Tetsuo

AU - Moriya, S.

AU - Arai, H.

AU - Higashi, M.

PY - 1994/12/1

Y1 - 1994/12/1

N2 - It is of practical importance to predict the stress corrosion crack (SCC) crack growth behavior in the pressure boundary components of nuclear power plants during operation. The establishment of the prediction method of SCC initiation and growth in light water reactor (LWR) environment is one of the essential steps in structural integrity assessment. In this paper, based upon a dissolution model, crack growth behavior of stress corrosion cracking of reactor pressure vessel steel of SA533B in simulated LWR environment under monotonic rising load (in other words Slow Strain Rate Test) and constant loading was simulated by the combination of FEM stress-strain analysis on growing crack and dissolution model. From the simulation results, the relationship between crack tip strain rate and crack propagation rate was discussed quantitatively. Crack growth rate can be evaluated in terms of both the crack tip strain rate and the crack tip solution chemistry such as, sulfur concentration and steady state dissolution rate (ISS).

AB - It is of practical importance to predict the stress corrosion crack (SCC) crack growth behavior in the pressure boundary components of nuclear power plants during operation. The establishment of the prediction method of SCC initiation and growth in light water reactor (LWR) environment is one of the essential steps in structural integrity assessment. In this paper, based upon a dissolution model, crack growth behavior of stress corrosion cracking of reactor pressure vessel steel of SA533B in simulated LWR environment under monotonic rising load (in other words Slow Strain Rate Test) and constant loading was simulated by the combination of FEM stress-strain analysis on growing crack and dissolution model. From the simulation results, the relationship between crack tip strain rate and crack propagation rate was discussed quantitatively. Crack growth rate can be evaluated in terms of both the crack tip strain rate and the crack tip solution chemistry such as, sulfur concentration and steady state dissolution rate (ISS).

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JF - American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

SN - 0277-027X

T2 - Proceedings of the 1994 Pressure Vessels and Piping Conference. Part 2 (of 19)

Y2 - 19 June 1994 through 23 June 1994

ER -

Improvement of predictive capability of environmentally assisted cracking by means of computer simulation of crack propagation

Abstract

ASJC Scopus subject areas

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