Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy

B.N. Singh, X. Huang, Seppo Tähtinen, Pekka Moilanen, P. Jacquet, J. Dekeyser

Research output: Book/ReportReportProfessional

Abstract

Traditionally, the effect of irradiation on mechanical properties of metals and alloys is determined using postirradiation tests carried out on pre-irradiated specimens and in the absence of irradiation environment. The results of these tests may not be representative of deformation behaviour of materials used in the structural components of a fission or fusion reactor where the materials will be exposed concurrently to displacement damage and external and/or internal stresses. In an effort to evaluate and understand the dynamic response of materials under these conditions, we have recently performed a series of uniaxial tensile tests on Fe-Cr and pure iron specimens in the BR-2 reactor at Mol (Belgium). The present report first provides a brief description of the test facilities and the procedure used for performing the in-reactor tests. The results on the mechanical response of materials during these tests are presented in the form of stressdisplacement dose and the conventional stress-strain curves. For comparison, the results of post-irradiation tests and tests carried out on unirradiated specimens are also presented. Results of microstructural investigations on the unirradiated and deformed, irradiated and undeformed, post-irradiation deformed and the in-reactor deformed specimens are also described. During the in-reactor tests the specimens of both Fe-Cr alloy and pure iron deform in a homogeneous manner and do not exhibit the phenomenon of yield drop. An increase in the preyield dose increases the yield stress but not the level of maximum flow stress during the in-reactor deformation of FeCr alloy. Neither the in-reactor nor the post-irradiation deformed specimens of Fe-Cr alloy and pure iron showed any evidence of cleared channel formation. Both in Fe-Cr and pure iron, the in-reactor deformation leads to accumulation of dislocations in a homogeneous fashion and only to a modest density. No dislocation cells are formed during the in-reactor or post-irradiation deformation of Fe-Cr and pure iron. Furthermore, in both cases, the slip systems even in the planes with Schmid factor value of almost zero get activated during the in-reactor as well as post-irradiation deformation. The main implications of these results are briefly discussed.
Original languageEnglish
Place of PublicationRoskilde, Denmark
Number of pages51
Publication statusPublished - 2007
MoE publication typeD4 Published development or research report or study

Publication series

NameRiso-R-1616 (EN)
PublisherRisø National Laboratory

Fingerprint

tensile deformation
reactors
iron
irradiation
Belgium
dosage
fusion reactors
test facilities
tensile tests
dynamic response
residual stress
fission
slip
mechanical properties
damage

Cite this

Singh, B. N., Huang, X., Tähtinen, S., Moilanen, P., Jacquet, P., & Dekeyser, J. (2007). Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy. Roskilde, Denmark. Risø-R, No. 1616(EN)
Singh, B.N. ; Huang, X. ; Tähtinen, Seppo ; Moilanen, Pekka ; Jacquet, P. ; Dekeyser, J. / Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy. Roskilde, Denmark, 2007. 51 p. (Risø-R; No. 1616(EN)).
@book{07ff8035a25a4eed9e9c7d718603746d,
title = "Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy",
abstract = "Traditionally, the effect of irradiation on mechanical properties of metals and alloys is determined using postirradiation tests carried out on pre-irradiated specimens and in the absence of irradiation environment. The results of these tests may not be representative of deformation behaviour of materials used in the structural components of a fission or fusion reactor where the materials will be exposed concurrently to displacement damage and external and/or internal stresses. In an effort to evaluate and understand the dynamic response of materials under these conditions, we have recently performed a series of uniaxial tensile tests on Fe-Cr and pure iron specimens in the BR-2 reactor at Mol (Belgium). The present report first provides a brief description of the test facilities and the procedure used for performing the in-reactor tests. The results on the mechanical response of materials during these tests are presented in the form of stressdisplacement dose and the conventional stress-strain curves. For comparison, the results of post-irradiation tests and tests carried out on unirradiated specimens are also presented. Results of microstructural investigations on the unirradiated and deformed, irradiated and undeformed, post-irradiation deformed and the in-reactor deformed specimens are also described. During the in-reactor tests the specimens of both Fe-Cr alloy and pure iron deform in a homogeneous manner and do not exhibit the phenomenon of yield drop. An increase in the preyield dose increases the yield stress but not the level of maximum flow stress during the in-reactor deformation of FeCr alloy. Neither the in-reactor nor the post-irradiation deformed specimens of Fe-Cr alloy and pure iron showed any evidence of cleared channel formation. Both in Fe-Cr and pure iron, the in-reactor deformation leads to accumulation of dislocations in a homogeneous fashion and only to a modest density. No dislocation cells are formed during the in-reactor or post-irradiation deformation of Fe-Cr and pure iron. Furthermore, in both cases, the slip systems even in the planes with Schmid factor value of almost zero get activated during the in-reactor as well as post-irradiation deformation. The main implications of these results are briefly discussed.",
author = "B.N. Singh and X. Huang and Seppo T{\"a}htinen and Pekka Moilanen and P. Jacquet and J. Dekeyser",
note = "Project code: 16166",
year = "2007",
language = "English",
isbn = "978-87-550-3620-8",
series = "Riso-R-1616 (EN)",
publisher = "Ris{\o} National Laboratory",

}

Singh, BN, Huang, X, Tähtinen, S, Moilanen, P, Jacquet, P & Dekeyser, J 2007, Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy. Risø-R, no. 1616(EN), Roskilde, Denmark.

Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy. / Singh, B.N.; Huang, X.; Tähtinen, Seppo; Moilanen, Pekka; Jacquet, P.; Dekeyser, J.

Roskilde, Denmark, 2007. 51 p. (Risø-R; No. 1616(EN)).

Research output: Book/ReportReportProfessional

TY - BOOK

T1 - Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy

AU - Singh, B.N.

AU - Huang, X.

AU - Tähtinen, Seppo

AU - Moilanen, Pekka

AU - Jacquet, P.

AU - Dekeyser, J.

N1 - Project code: 16166

PY - 2007

Y1 - 2007

N2 - Traditionally, the effect of irradiation on mechanical properties of metals and alloys is determined using postirradiation tests carried out on pre-irradiated specimens and in the absence of irradiation environment. The results of these tests may not be representative of deformation behaviour of materials used in the structural components of a fission or fusion reactor where the materials will be exposed concurrently to displacement damage and external and/or internal stresses. In an effort to evaluate and understand the dynamic response of materials under these conditions, we have recently performed a series of uniaxial tensile tests on Fe-Cr and pure iron specimens in the BR-2 reactor at Mol (Belgium). The present report first provides a brief description of the test facilities and the procedure used for performing the in-reactor tests. The results on the mechanical response of materials during these tests are presented in the form of stressdisplacement dose and the conventional stress-strain curves. For comparison, the results of post-irradiation tests and tests carried out on unirradiated specimens are also presented. Results of microstructural investigations on the unirradiated and deformed, irradiated and undeformed, post-irradiation deformed and the in-reactor deformed specimens are also described. During the in-reactor tests the specimens of both Fe-Cr alloy and pure iron deform in a homogeneous manner and do not exhibit the phenomenon of yield drop. An increase in the preyield dose increases the yield stress but not the level of maximum flow stress during the in-reactor deformation of FeCr alloy. Neither the in-reactor nor the post-irradiation deformed specimens of Fe-Cr alloy and pure iron showed any evidence of cleared channel formation. Both in Fe-Cr and pure iron, the in-reactor deformation leads to accumulation of dislocations in a homogeneous fashion and only to a modest density. No dislocation cells are formed during the in-reactor or post-irradiation deformation of Fe-Cr and pure iron. Furthermore, in both cases, the slip systems even in the planes with Schmid factor value of almost zero get activated during the in-reactor as well as post-irradiation deformation. The main implications of these results are briefly discussed.

AB - Traditionally, the effect of irradiation on mechanical properties of metals and alloys is determined using postirradiation tests carried out on pre-irradiated specimens and in the absence of irradiation environment. The results of these tests may not be representative of deformation behaviour of materials used in the structural components of a fission or fusion reactor where the materials will be exposed concurrently to displacement damage and external and/or internal stresses. In an effort to evaluate and understand the dynamic response of materials under these conditions, we have recently performed a series of uniaxial tensile tests on Fe-Cr and pure iron specimens in the BR-2 reactor at Mol (Belgium). The present report first provides a brief description of the test facilities and the procedure used for performing the in-reactor tests. The results on the mechanical response of materials during these tests are presented in the form of stressdisplacement dose and the conventional stress-strain curves. For comparison, the results of post-irradiation tests and tests carried out on unirradiated specimens are also presented. Results of microstructural investigations on the unirradiated and deformed, irradiated and undeformed, post-irradiation deformed and the in-reactor deformed specimens are also described. During the in-reactor tests the specimens of both Fe-Cr alloy and pure iron deform in a homogeneous manner and do not exhibit the phenomenon of yield drop. An increase in the preyield dose increases the yield stress but not the level of maximum flow stress during the in-reactor deformation of FeCr alloy. Neither the in-reactor nor the post-irradiation deformed specimens of Fe-Cr alloy and pure iron showed any evidence of cleared channel formation. Both in Fe-Cr and pure iron, the in-reactor deformation leads to accumulation of dislocations in a homogeneous fashion and only to a modest density. No dislocation cells are formed during the in-reactor or post-irradiation deformation of Fe-Cr and pure iron. Furthermore, in both cases, the slip systems even in the planes with Schmid factor value of almost zero get activated during the in-reactor as well as post-irradiation deformation. The main implications of these results are briefly discussed.

M3 - Report

SN - 978-87-550-3620-8

T3 - Riso-R-1616 (EN)

BT - Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy

CY - Roskilde, Denmark

ER -

Singh BN, Huang X, Tähtinen S, Moilanen P, Jacquet P, Dekeyser J. Final report on in-reactor uniaxial tensile deformation of pure iron and Fe-Cr alloy. Roskilde, Denmark, 2007. 51 p. (Risø-R; No. 1616(EN)).