In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC

B.N. Singh (Corresponding Author), Seppo Tähtinen, P. Moilanen, P. Jacquet, J. Dekeyser

Research output: Contribution to journalArticleScientificpeer-review

12 Citations (Scopus)

Abstract

Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12%. The preliminary results are briefly described and discussed in the present note.
Original languageEnglish
Pages (from-to)299-304
Number of pages6
JournalJournal of Nuclear Materials
Volume320
Issue number3
DOIs
Publication statusPublished - 2003
MoE publication typeA1 Journal article-refereed

Fingerprint

Tensile testing
Nuclear reactors
Dosimetry
strain rate
Strain rate
Copper
Elongation
reactors
Irradiation
Plastics
copper
Experiments
Temperature
elongation
fission
plastics
damage
dosage
irradiation
temperature

Keywords

  • irradiation
  • irradiation damage
  • irradiation embrittlement
  • neutron irradiation
  • deformation

Cite this

Singh, B.N. ; Tähtinen, Seppo ; Moilanen, P. ; Jacquet, P. ; Dekeyser, J. / In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC. In: Journal of Nuclear Materials. 2003 ; Vol. 320, No. 3. pp. 299-304.
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In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC. / Singh, B.N. (Corresponding Author); Tähtinen, Seppo; Moilanen, P.; Jacquet, P.; Dekeyser, J.

In: Journal of Nuclear Materials, Vol. 320, No. 3, 2003, p. 299-304.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC

AU - Singh, B.N.

AU - Tähtinen, Seppo

AU - Moilanen, P.

AU - Jacquet, P.

AU - Dekeyser, J.

PY - 2003

Y1 - 2003

N2 - Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12%. The preliminary results are briefly described and discussed in the present note.

AB - Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12%. The preliminary results are briefly described and discussed in the present note.

KW - irradiation

KW - irradiation damage

KW - irradiation embrittlement

KW - neutron irradiation

KW - deformation

U2 - 10.1016/S0022-3115(03)00234-4

DO - 10.1016/S0022-3115(03)00234-4

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SP - 299

EP - 304

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

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ER -