Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences

D. L. Porter; F. A. Garner

doi:10.1016/0022-3115(88)90089-X

Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences

D. L. Porter
, F. A. Garner

Research output: Contribution to journal › Article › peer-review

41 Scopus citations

Abstract

The irradiation-induced creep and swelling of AISI 316 stainless steel have been investigated at two temperatures (400 and 550°C) to very high neutron fluences. It is shown that creep and swelling can be considered as interactive phenomena with several stages of creep related to the total amount of accumulated swelling. The final stage involves the apparent cessation of creep and has been observed only at the higher irradiation temperature. The development of a coincident and severe ex-reactor embrittlement problem after irradiation at 400° C appears also to be separately related to the development of substantial swelling. This latter phenomenom was not observed at 550° C. The mechanisms thought to be possibly responsible for each of these two phenomena are discussed in detail.

Original language	English
Pages (from-to)	114-121
Number of pages	8
Journal	Journal of Nuclear Materials
Volume	159
Issue number	C
DOIs	https://doi.org/10.1016/0022-3115(88)90089-X
State	Published - Oct 1988
Externally published	Yes

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title = "Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences",

abstract = "The irradiation-induced creep and swelling of AISI 316 stainless steel have been investigated at two temperatures (400 and 550°C) to very high neutron fluences. It is shown that creep and swelling can be considered as interactive phenomena with several stages of creep related to the total amount of accumulated swelling. The final stage involves the apparent cessation of creep and has been observed only at the higher irradiation temperature. The development of a coincident and severe ex-reactor embrittlement problem after irradiation at 400° C appears also to be separately related to the development of substantial swelling. This latter phenomenom was not observed at 550° C. The mechanisms thought to be possibly responsible for each of these two phenomena are discussed in detail.",

author = "Porter, \{D. L.\} and Garner, \{F. A.\}",

note = "Funding Information: * Work supported by the US Department of Energy under Contract DE-ACO6-75RLO 1830 and W-31-109-38.",

year = "1988",

month = oct,

doi = "10.1016/0022-3115(88)90089-X",

language = "English",

volume = "159",

pages = "114--121",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

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TY - JOUR

T1 - Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences

AU - Porter, D. L.

AU - Garner, F. A.

N1 - Funding Information: * Work supported by the US Department of Energy under Contract DE-ACO6-75RLO 1830 and W-31-109-38.

PY - 1988/10

Y1 - 1988/10

N2 - The irradiation-induced creep and swelling of AISI 316 stainless steel have been investigated at two temperatures (400 and 550°C) to very high neutron fluences. It is shown that creep and swelling can be considered as interactive phenomena with several stages of creep related to the total amount of accumulated swelling. The final stage involves the apparent cessation of creep and has been observed only at the higher irradiation temperature. The development of a coincident and severe ex-reactor embrittlement problem after irradiation at 400° C appears also to be separately related to the development of substantial swelling. This latter phenomenom was not observed at 550° C. The mechanisms thought to be possibly responsible for each of these two phenomena are discussed in detail.

AB - The irradiation-induced creep and swelling of AISI 316 stainless steel have been investigated at two temperatures (400 and 550°C) to very high neutron fluences. It is shown that creep and swelling can be considered as interactive phenomena with several stages of creep related to the total amount of accumulated swelling. The final stage involves the apparent cessation of creep and has been observed only at the higher irradiation temperature. The development of a coincident and severe ex-reactor embrittlement problem after irradiation at 400° C appears also to be separately related to the development of substantial swelling. This latter phenomenom was not observed at 550° C. The mechanisms thought to be possibly responsible for each of these two phenomena are discussed in detail.

UR - https://www.scopus.com/pages/publications/0024087881

U2 - 10.1016/0022-3115(88)90089-X

DO - 10.1016/0022-3115(88)90089-X

M3 - Article

AN - SCOPUS:0024087881

SN - 0022-3115

VL - 159

SP - 114

EP - 121

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - C

ER -

Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences

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