Irradiation Creep and Irradiation Stress Relaxation of 316 and 304L Stainless Steels in Thermal and Fast Neutron Spectrum Reactors

Foster, Jann P; Karlsen, T. M.

doi:10.1002/9781118456835.ch139

Cited by 4 publications

(4 citation statements)

References 4 publications

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“…Understanding on irradiation creep has obtained mainly from data at temperatures higher than 400 • C [278] and experimental data at LWR-relevant temperatures (280-370 • C) are scarce [279,280]. Recently data on irradiation creep and stress relaxation at temperatures around 300 • C have been accumulated by MTR irradiation experiments in the last decade [281][282][283][284][285][286][287]. Figure 22 shows the data of irradiation stress relaxation in type 304 and 316L SSs at 288 • C [280][281][282][283][284].…”

Section: Irradiation Creep and Stress Relaxationmentioning

confidence: 99%

Current understanding of radiation-induced degradation in light water reactor structural materials

Fukuya¹

2013

Journal of Nuclear Science and Technology

161

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Current phenomenological knowledge and understanding of mechanisms are reviewed for radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted stress corrosion cracking of core internals of stainless steels. Accumulated test data of irradiated materials in light water reactors and microscopic analyses by using state-of-the-art techniques such as a three-dimensional atom probe and electron backscatter diffraction have significantly increased knowledge about microstructural features. Characteristics of solute clusters and deformation microstructures and their contributions to macroscopic material property changes have been clarified to a large extent, which provide keys to understand in the degradation mechanisms. However, there are still fundamental research issues that merit study for long-term operation of reactors that requires reliable quantitative prediction of radiation-induced degradation of component materials in low-dose rate high-dose conditions.

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Section: Irradiation Creep and Stress Relaxationmentioning

confidence: 99%

Current understanding of radiation-induced degradation in light water reactor structural materials

Fukuya¹

2013

Journal of Nuclear Science and Technology

161

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“…The creep tests take advantage of in-pile instrumentation and control systems native to the Halden facility to collect accurate in-pile data with reliable environmental controls. Detailed description of this test rig is provided elsewhere [24], but briefly, it utilizes adjustable mixture gas flow in annular regions of the capsule, coupled with multiple thermocouples in each capsule for precise temperature control along the length of the specimen. The stress on the creep specimens is controlled by direct gas pressure control inside a bellow attached to the creep specimen that is gripped at the other end.…”

Section: Experiments Descriptionmentioning

confidence: 99%

Input Correlations for Irradiation Creep of FeCrAl and SiC Based on In-Pile Halden Test Results

Terrani

Karlsen

Yamamoto

2016

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Swelling and creep behavior of wrought FeCrAl alloys and CVD-SiC, two candidate accident tolerant fuel cladding materials, are being examined using in-pile tests at the Halden reactor. The outcome of these tests are material property correlations that are inputs into fuel performance analysis tools. The results are discussed and compared with what is available in literature from irradiation experiments in other reactors or out-of-pile tests. Specific recommendation on what correlations should be used for swelling, thermal, and irradiation creep for each material are provided in this document.

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“…The creep tests take advantage of in-pile instrumentation and control systems native to the Halden facility to collect accurate in-pile data with reliable environmental controls. Detailed description of this test rig is provided elsewhere [10], but briefly, they utilize adjustable mixture gas flow in annular regions of the capsule, coupled with multiple thermocouples in each capsule for precise temperature control along the length of the specimen. The stress on the creep specimens is controlled by direct gas pressure control inside a bellow attached to the creep specimen that is gripped at the other end.…”

Section: Experiments Descriptionmentioning

confidence: 99%

Report On Design And Preliminary Data Of Halden In-Pile Creep Rig

Terrani

Karlsen

Yamamoto

2015

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Irradiation Creep and Irradiation Stress Relaxation of 316 and 304L Stainless Steels in Thermal and Fast Neutron Spectrum Reactors

Cited by 4 publications

References 4 publications

Current understanding of radiation-induced degradation in light water reactor structural materials

Current understanding of radiation-induced degradation in light water reactor structural materials

Input Correlations for Irradiation Creep of FeCrAl and SiC Based on In-Pile Halden Test Results

Report On Design And Preliminary Data Of Halden In-Pile Creep Rig

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