Degraded piping program - phase II progress

Wilkowski, G.; Ahmad, Jalees; Barnes, David; Brust, F. W.; Ghadiali, N.; Guerrieri, Daduí Cordeiro; Kiefner, J.F.; Kramer, G.; Landow, M.; Marschall, C.W.; Maxey, W.A.; Nakagaki, Michihiko; Papaspyropoulos, V.; Pasupathi, V.; Scott, Paul

doi:10.1016/0029-5493(87)90166-x

Cited by 25 publications

(4 citation statements)

References 2 publications

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“…17. 15,[38][39][40][41] For wrought austenitic SSs, 3 the J I c values at temperatures up to 550°C are typically >400 kJ/m 2 ; experimental J Ic for Heats L2 and L20 is in the range of 150-230 and 80-120 kJ/m 2 , respectively. The commercial Heats C16 and C19 show the very high fracture toughnesses expected for Type 304 SSs.…”

Section: Nonirradiated Type 304 Stainless Steelmentioning

confidence: 99%

Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

Chopra¹,

Gruber²,

Shack³

2003

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Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of reactor pressure vessels because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. Experimental data are presented on fracture toughness and crack growth rates (CGRs) of austenitic SSs irradiated to fluence levels up to 2.0 x 10 21 n/cm 2 (E > 1 MeV) (ª3.0 dpa) at ª288°C. Crack growth tests were conducted under cycling loading and long hold time trapezoidal loading in simulated boiling water reactor (BWR) environments, and fracture toughness tests were conducted in air. Neutron irradiation at 288°C decreases the fracture toughness of the steels; the data from commercial heats fall within the scatter band for the data obtained at higher temperatures. In addition, the results indicate significant enhancement of CGRs of the irradiated steels in normal water chemistry BWR environment; the CGRs for irradiated steels are a factor of ª5 higher than the disposition curve proposed for sensitized austenitic SSs. The rates decreased by more than an order of magnitude in low-dissolved-oxygen BWR environment.

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Section: Nonirradiated Type 304 Stainless Steelmentioning

confidence: 99%

Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

Chopra¹,

Gruber²,

Shack³

2003

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“…If the weld material is so ductile that the plastic deformation in the parent material extends to general yield, crack extension can be described in terms of the attainment of a critical net-section stress across the uncracked section of the structure [3], the appropriate net-section stress value being op, the yield stress of the parent material. The condition that failure be described in these terms is [4] ESw/o-pC >/f(C/hl, C/h 2 ---) where E is Young's modulus, C is the crack size and h v h 2 etc.…”

mentioning

confidence: 99%

The failure of an engineering structure containing a weld crack: Weld material is ductile

Smith

1990

Int J Fract

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“…The three LBB seminars that were held in conjunction with the IPIRG Program were in Columbus (October 1985), Tokyo (May 1987), and Taipei (May 1989) (Refs. 1 .l, 1.43, and 1.44).…”

Section: Why Did We Need the Ipirg Program?mentioning

confidence: 99%

International Piping Integrity Research Group (IPIRG) Program. Final report

Wilkowski¹,

Schmidt²,

Scott³

1997

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This is the fmal report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States.The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events.To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility.This report: ( 1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program.

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Degraded piping program - phase II progress

Cited by 25 publications

References 2 publications

Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

The failure of an engineering structure containing a weld crack: Weld material is ductile

International Piping Integrity Research Group (IPIRG) Program. Final report

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