Abstract
In order to validate the applicability of copper alloys in the structural components of ITER, the effect of neutron irradiation on the fracture toughness behaviour has to be studied.
Fracture toughness testing of irradiated materials requires the use of miniaturised specimens and the verification of specimen size effects on fracture toughness test results. In the present study the effects of specimen type, size as well as temperature on the ductile tearing fracture resistance behaviour of CuCrZr alloy will be shown.
The applicability of miniaturised specimens for fracture resistance curve determination is considered by studying the allowable crack extension with which the miniaturised specimens still have similar fracture resistance curves as full-size specimens.
The crack length and J-integral values will be compared to ASTM standard requirements for the maximum allowable crack extension and J-integral values in the fracture resistance test.
| Original language | English |
|---|---|
| Pages (from-to) | 462-465 |
| Journal | Journal of Nuclear Materials |
| Volume | 258-263 |
| Issue number | Part 1 |
| DOIs | |
| Publication status | Published - 1998 |
| MoE publication type | A1 Journal article-refereed |
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Effect of specimen type and size on fracture resistance curve determination of CuCrZr alloy. / Karjalainen-Roikonen, Päivi; Pyykkönen, Mika; Tähtinen, Seppo (Corresponding Author).
In: Journal of Nuclear Materials, Vol. 258-263, No. Part 1, 1998, p. 462-465.Research output: Contribution to journal › Article › Scientific › peer-review
TY - JOUR
T1 - Effect of specimen type and size on fracture resistance curve determination of CuCrZr alloy
AU - Karjalainen-Roikonen, Päivi
AU - Pyykkönen, Mika
AU - Tähtinen, Seppo
PY - 1998
Y1 - 1998
N2 - The precipitation hardened copper alloy CuCrZr is one of the candidate materials for the first wall and divertor components of ITER. In order to validate the applicability of copper alloys in the structural components of ITER, the effect of neutron irradiation on the fracture toughness behaviour has to be studied. Fracture toughness testing of irradiated materials requires the use of miniaturised specimens and the verification of specimen size effects on fracture toughness test results. In the present study the effects of specimen type, size as well as temperature on the ductile tearing fracture resistance behaviour of CuCrZr alloy will be shown. The applicability of miniaturised specimens for fracture resistance curve determination is considered by studying the allowable crack extension with which the miniaturised specimens still have similar fracture resistance curves as full-size specimens. The crack length and J-integral values will be compared to ASTM standard requirements for the maximum allowable crack extension and J-integral values in the fracture resistance test.
AB - The precipitation hardened copper alloy CuCrZr is one of the candidate materials for the first wall and divertor components of ITER. In order to validate the applicability of copper alloys in the structural components of ITER, the effect of neutron irradiation on the fracture toughness behaviour has to be studied. Fracture toughness testing of irradiated materials requires the use of miniaturised specimens and the verification of specimen size effects on fracture toughness test results. In the present study the effects of specimen type, size as well as temperature on the ductile tearing fracture resistance behaviour of CuCrZr alloy will be shown. The applicability of miniaturised specimens for fracture resistance curve determination is considered by studying the allowable crack extension with which the miniaturised specimens still have similar fracture resistance curves as full-size specimens. The crack length and J-integral values will be compared to ASTM standard requirements for the maximum allowable crack extension and J-integral values in the fracture resistance test.
U2 - 10.1016/S0022-3115(98)00101-9
DO - 10.1016/S0022-3115(98)00101-9
M3 - Article
VL - 258-263
SP - 462
EP - 465
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
IS - Part 1
ER -