Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behaviors

L. Debarberis, F. Sevini, B. Acosta, A. Kryukov, Y. Nikolaev, A. Amaev, Matti Valo

Research output: Contribution to journalArticleScientificpeer-review

23 Citations (Scopus)

Abstract

The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors is a key issue for the plant lifetime assessment and life extension through mitigation methods like annealing and much effort have been done in the last decades to tackle such complex issue.
The reactor pressure vessel (RPV) material of nuclear power plants is exposed to neutron irradiation during its operation.
Such exposure is generally inducing a degradation of the mechanical and physical properties of the materials, e.g. an increase of the ductile to brittle, DBT, transition temperature and a decrease of the upper shelf energy.

The different response of materials to neutron irradiation, even many factors are also playing significant role, is mainly due, for a given exposure, to the chemical composition of the materials. In particular, for the RPV steel, elements like phosphorus, P, copper, Cu, and nickel, Ni, are playing a key role.

A parametric study of the response to neutron irradiation of 32 different model alloys with parametric variation of elements (Ni from 0.004 to ∼2 wt%, P from 0.001 to 0.039 wt%, Cu from 0.005 to ∼1 wt%) has been recently completed within the frame of the European Network AMES and EC-JRC AMES Institutional project [1].

Such study on model alloys reveals to be a fundamental tool to understand the individual role of each element and synergisms.

To demonstrate the usefulness of the study to commercial RPV steels, an analysis of the results and the similitude of behavior between model alloys and available RPV commercial steels has been carried out and the results are presented in this paper.

Original languageEnglish
Pages (from-to)637-642
JournalInternational Journal of Pressure Vessels and Piping
Volume79
Issue number8-10
DOIs
Publication statusPublished - 2002
MoE publication typeA1 Journal article-refereed

Fingerprint

Steel analysis
Embrittlement
Neutron irradiation
Pressure vessels
Irradiation
Steel structures
Steel
Nuclear reactors
Nickel
Chemical elements
Phosphorus
Nuclear power plants
Superconducting transition temperature
Copper
Physical properties
Annealing
Degradation
Mechanical properties
Chemical analysis

Keywords

  • reactor pressure vessel
  • model alloys
  • high flux reactor

Cite this

Debarberis, L. ; Sevini, F. ; Acosta, B. ; Kryukov, A. ; Nikolaev, Y. ; Amaev, A. ; Valo, Matti. / Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behaviors. In: International Journal of Pressure Vessels and Piping. 2002 ; Vol. 79, No. 8-10. pp. 637-642.
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abstract = "The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors is a key issue for the plant lifetime assessment and life extension through mitigation methods like annealing and much effort have been done in the last decades to tackle such complex issue. The reactor pressure vessel (RPV) material of nuclear power plants is exposed to neutron irradiation during its operation. Such exposure is generally inducing a degradation of the mechanical and physical properties of the materials, e.g. an increase of the ductile to brittle, DBT, transition temperature and a decrease of the upper shelf energy.The different response of materials to neutron irradiation, even many factors are also playing significant role, is mainly due, for a given exposure, to the chemical composition of the materials. In particular, for the RPV steel, elements like phosphorus, P, copper, Cu, and nickel, Ni, are playing a key role.A parametric study of the response to neutron irradiation of 32 different model alloys with parametric variation of elements (Ni from 0.004 to ∼2 wt{\%}, P from 0.001 to 0.039 wt{\%}, Cu from 0.005 to ∼1 wt{\%}) has been recently completed within the frame of the European Network AMES and EC-JRC AMES Institutional project [1].Such study on model alloys reveals to be a fundamental tool to understand the individual role of each element and synergisms.To demonstrate the usefulness of the study to commercial RPV steels, an analysis of the results and the similitude of behavior between model alloys and available RPV commercial steels has been carried out and the results are presented in this paper.",
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author = "L. Debarberis and F. Sevini and B. Acosta and A. Kryukov and Y. Nikolaev and A. Amaev and Matti Valo",
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Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behaviors. / Debarberis, L.; Sevini, F.; Acosta, B.; Kryukov, A.; Nikolaev, Y.; Amaev, A.; Valo, Matti.

In: International Journal of Pressure Vessels and Piping, Vol. 79, No. 8-10, 2002, p. 637-642.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behaviors

AU - Debarberis, L.

AU - Sevini, F.

AU - Acosta, B.

AU - Kryukov, A.

AU - Nikolaev, Y.

AU - Amaev, A.

AU - Valo, Matti

PY - 2002

Y1 - 2002

N2 - The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors is a key issue for the plant lifetime assessment and life extension through mitigation methods like annealing and much effort have been done in the last decades to tackle such complex issue. The reactor pressure vessel (RPV) material of nuclear power plants is exposed to neutron irradiation during its operation. Such exposure is generally inducing a degradation of the mechanical and physical properties of the materials, e.g. an increase of the ductile to brittle, DBT, transition temperature and a decrease of the upper shelf energy.The different response of materials to neutron irradiation, even many factors are also playing significant role, is mainly due, for a given exposure, to the chemical composition of the materials. In particular, for the RPV steel, elements like phosphorus, P, copper, Cu, and nickel, Ni, are playing a key role.A parametric study of the response to neutron irradiation of 32 different model alloys with parametric variation of elements (Ni from 0.004 to ∼2 wt%, P from 0.001 to 0.039 wt%, Cu from 0.005 to ∼1 wt%) has been recently completed within the frame of the European Network AMES and EC-JRC AMES Institutional project [1].Such study on model alloys reveals to be a fundamental tool to understand the individual role of each element and synergisms.To demonstrate the usefulness of the study to commercial RPV steels, an analysis of the results and the similitude of behavior between model alloys and available RPV commercial steels has been carried out and the results are presented in this paper.

AB - The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors is a key issue for the plant lifetime assessment and life extension through mitigation methods like annealing and much effort have been done in the last decades to tackle such complex issue. The reactor pressure vessel (RPV) material of nuclear power plants is exposed to neutron irradiation during its operation. Such exposure is generally inducing a degradation of the mechanical and physical properties of the materials, e.g. an increase of the ductile to brittle, DBT, transition temperature and a decrease of the upper shelf energy.The different response of materials to neutron irradiation, even many factors are also playing significant role, is mainly due, for a given exposure, to the chemical composition of the materials. In particular, for the RPV steel, elements like phosphorus, P, copper, Cu, and nickel, Ni, are playing a key role.A parametric study of the response to neutron irradiation of 32 different model alloys with parametric variation of elements (Ni from 0.004 to ∼2 wt%, P from 0.001 to 0.039 wt%, Cu from 0.005 to ∼1 wt%) has been recently completed within the frame of the European Network AMES and EC-JRC AMES Institutional project [1].Such study on model alloys reveals to be a fundamental tool to understand the individual role of each element and synergisms.To demonstrate the usefulness of the study to commercial RPV steels, an analysis of the results and the similitude of behavior between model alloys and available RPV commercial steels has been carried out and the results are presented in this paper.

KW - reactor pressure vessel

KW - model alloys

KW - high flux reactor

U2 - 10.1016/S0308-0161(02)00066-2

DO - 10.1016/S0308-0161(02)00066-2

M3 - Article

VL - 79

SP - 637

EP - 642

JO - International Journal of Pressure Vessels and Piping

JF - International Journal of Pressure Vessels and Piping

SN - 0308-0161

IS - 8-10

ER -