Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 1

B.N. Singh, Seppo Tähtinen, Pekka Moilanen, P. Jacquet, J. Dekeyser, D.J. Edwards, M. Li, J.F. Stubbins

Research output: Book/ReportReport

Abstract

At present, practically nothing is known about the deformation
behaviour of materials subjected simultaneously to external cyclic
force and neutron irradiation. The main objective of the present
work is to determine experimentally the mechanical response and
resulting microstructural changes in CuCrZr(HT1) alloy exposed
concurrently to flux of neutrons and creep-fatigue cyclic loading
directly in a fission reactor. Special experimental facilities were
designed and fabricated for this purpose. A number of in-reactor
creep-fatigue experiments were successfully carried out in the BR-2
reactor at Mol (Belgium). In the present report we first describe the
experimental facilities and the details of the in-reactor creep-fatigue
experiments carried out at 363 and 343K at a strain amplitude of
0.5% with holdtimes of 10 and 100s, respectively. For comparison
purposes, similar creep-fatigue tests were performed outside of the
reactor. (i.e. in the absence of neutron irradiation).

During in-reactor tests, the mechanical response was continuously
registered throughout the whole test. The results are first presented
in the form of hysteresis loops confirming that the nature of
deformation during these tests was truly cyclic. The temporal
evolution of the stress response in the specimens is presented in the
form of the average maximum stress amplitude as a function of the
number of cycles as well as a function of displacement dose
accumulated during the tests. The results illustrate the nature and
magnitude of cyclic hardening as well as softening as a function of
the number of cycles and displacement dose. Details of the
microstructure were investigated using TEM and STEM techniques.
The fracture surface morphology was investigated using SEM
technique. Both mechanical and microstructural results are briefly
discussed. The main conclusion emerging from the limited amount
of present results is that neither the irradiation nor the duration of
the holdtime have any significant effect on the lifetime (in terms of
number of cycle to failure) of the material.
Original languageEnglish
Number of pages45
Publication statusPublished - 2007
MoE publication typeD4 Published development or research report or study

Publication series

SeriesRisø-R
NumberR-1571(EN)
ISSN0106-2840

Fingerprint

reactors
neutron irradiation
cycles
Belgium
irradiation
fatigue tests
hardening
softening
fission
emerging
hysteresis
neutrons
life (durability)
dosage
transmission electron microscopy

Cite this

Singh, B. N., Tähtinen, S., Moilanen, P., Jacquet, P., Dekeyser, J., Edwards, D. J., ... Stubbins, J. F. (2007). Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 1. Risø-R, No. R-1571(EN)
Singh, B.N. ; Tähtinen, Seppo ; Moilanen, Pekka ; Jacquet, P. ; Dekeyser, J. ; Edwards, D.J. ; Li, M. ; Stubbins, J.F. / Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy : COFAT 1. 2007. 45 p. (Risø-R; No. R-1571(EN)).
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abstract = "At present, practically nothing is known about the deformationbehaviour of materials subjected simultaneously to external cyclicforce and neutron irradiation. The main objective of the presentwork is to determine experimentally the mechanical response andresulting microstructural changes in CuCrZr(HT1) alloy exposedconcurrently to flux of neutrons and creep-fatigue cyclic loadingdirectly in a fission reactor. Special experimental facilities weredesigned and fabricated for this purpose. A number of in-reactorcreep-fatigue experiments were successfully carried out in the BR-2reactor at Mol (Belgium). In the present report we first describe theexperimental facilities and the details of the in-reactor creep-fatigueexperiments carried out at 363 and 343K at a strain amplitude of0.5{\%} with holdtimes of 10 and 100s, respectively. For comparisonpurposes, similar creep-fatigue tests were performed outside of thereactor. (i.e. in the absence of neutron irradiation).During in-reactor tests, the mechanical response was continuouslyregistered throughout the whole test. The results are first presentedin the form of hysteresis loops confirming that the nature ofdeformation during these tests was truly cyclic. The temporalevolution of the stress response in the specimens is presented in theform of the average maximum stress amplitude as a function of thenumber of cycles as well as a function of displacement doseaccumulated during the tests. The results illustrate the nature andmagnitude of cyclic hardening as well as softening as a function ofthe number of cycles and displacement dose. Details of themicrostructure were investigated using TEM and STEM techniques.The fracture surface morphology was investigated using SEMtechnique. Both mechanical and microstructural results are brieflydiscussed. The main conclusion emerging from the limited amountof present results is that neither the irradiation nor the duration ofthe holdtime have any significant effect on the lifetime (in terms ofnumber of cycle to failure) of the material.",
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Singh, BN, Tähtinen, S, Moilanen, P, Jacquet, P, Dekeyser, J, Edwards, DJ, Li, M & Stubbins, JF 2007, Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 1. Risø-R, no. R-1571(EN).

Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy : COFAT 1. / Singh, B.N.; Tähtinen, Seppo; Moilanen, Pekka; Jacquet, P.; Dekeyser, J.; Edwards, D.J.; Li, M.; Stubbins, J.F.

2007. 45 p. (Risø-R; No. R-1571(EN)).

Research output: Book/ReportReport

TY - BOOK

T1 - Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy

T2 - COFAT 1

AU - Singh, B.N.

AU - Tähtinen, Seppo

AU - Moilanen, Pekka

AU - Jacquet, P.

AU - Dekeyser, J.

AU - Edwards, D.J.

AU - Li, M.

AU - Stubbins, J.F.

N1 - Project code: 16166

PY - 2007

Y1 - 2007

N2 - At present, practically nothing is known about the deformationbehaviour of materials subjected simultaneously to external cyclicforce and neutron irradiation. The main objective of the presentwork is to determine experimentally the mechanical response andresulting microstructural changes in CuCrZr(HT1) alloy exposedconcurrently to flux of neutrons and creep-fatigue cyclic loadingdirectly in a fission reactor. Special experimental facilities weredesigned and fabricated for this purpose. A number of in-reactorcreep-fatigue experiments were successfully carried out in the BR-2reactor at Mol (Belgium). In the present report we first describe theexperimental facilities and the details of the in-reactor creep-fatigueexperiments carried out at 363 and 343K at a strain amplitude of0.5% with holdtimes of 10 and 100s, respectively. For comparisonpurposes, similar creep-fatigue tests were performed outside of thereactor. (i.e. in the absence of neutron irradiation).During in-reactor tests, the mechanical response was continuouslyregistered throughout the whole test. The results are first presentedin the form of hysteresis loops confirming that the nature ofdeformation during these tests was truly cyclic. The temporalevolution of the stress response in the specimens is presented in theform of the average maximum stress amplitude as a function of thenumber of cycles as well as a function of displacement doseaccumulated during the tests. The results illustrate the nature andmagnitude of cyclic hardening as well as softening as a function ofthe number of cycles and displacement dose. Details of themicrostructure were investigated using TEM and STEM techniques.The fracture surface morphology was investigated using SEMtechnique. Both mechanical and microstructural results are brieflydiscussed. The main conclusion emerging from the limited amountof present results is that neither the irradiation nor the duration ofthe holdtime have any significant effect on the lifetime (in terms ofnumber of cycle to failure) of the material.

AB - At present, practically nothing is known about the deformationbehaviour of materials subjected simultaneously to external cyclicforce and neutron irradiation. The main objective of the presentwork is to determine experimentally the mechanical response andresulting microstructural changes in CuCrZr(HT1) alloy exposedconcurrently to flux of neutrons and creep-fatigue cyclic loadingdirectly in a fission reactor. Special experimental facilities weredesigned and fabricated for this purpose. A number of in-reactorcreep-fatigue experiments were successfully carried out in the BR-2reactor at Mol (Belgium). In the present report we first describe theexperimental facilities and the details of the in-reactor creep-fatigueexperiments carried out at 363 and 343K at a strain amplitude of0.5% with holdtimes of 10 and 100s, respectively. For comparisonpurposes, similar creep-fatigue tests were performed outside of thereactor. (i.e. in the absence of neutron irradiation).During in-reactor tests, the mechanical response was continuouslyregistered throughout the whole test. The results are first presentedin the form of hysteresis loops confirming that the nature ofdeformation during these tests was truly cyclic. The temporalevolution of the stress response in the specimens is presented in theform of the average maximum stress amplitude as a function of thenumber of cycles as well as a function of displacement doseaccumulated during the tests. The results illustrate the nature andmagnitude of cyclic hardening as well as softening as a function ofthe number of cycles and displacement dose. Details of themicrostructure were investigated using TEM and STEM techniques.The fracture surface morphology was investigated using SEMtechnique. Both mechanical and microstructural results are brieflydiscussed. The main conclusion emerging from the limited amountof present results is that neither the irradiation nor the duration ofthe holdtime have any significant effect on the lifetime (in terms ofnumber of cycle to failure) of the material.

M3 - Report

SN - 87-550-3538-8

T3 - Risø-R

BT - Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy

ER -

Singh BN, Tähtinen S, Moilanen P, Jacquet P, Dekeyser J, Edwards DJ et al. Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 1. 2007. 45 p. (Risø-R; No. R-1571(EN)).