MECHANISM OF CHANGE IN VVER-440,-1000 VESSEL MATERIAL PROPERTIES IN IRRADIATION-RECOVERY ANNEALING-IRRADIATION CYCLE

被引：3

作者：

Gurovich, B. A. ^{[1
]}

Kuleshova, E. A. ^{[1
]}

Mal'tsev, D. A. ^{[1
]}

Semchenkov, Yu. M. ^{[1
]}

Frolov, A. S. ^{[1
]}

Shtrombakh, Ya. I. ^{[1
]}

Shutikov, A. V. ^{[2
]}

机构：

[1] Natl Res Ctr, Kurchatov Inst, Moscow, Russia

[2] Rosenergoatom Concern, Moscow, Russia

来源：

ATOMIC ENERGY | 2018年 / 125卷 / 02期

关键词：

EVOLUTION; STEELS; NANOSTRUCTURE; EMBRITTLEMENT;

D O I：

10.1007/s10512-018-0448-8

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The efficacy of recovery annealing of weld-seam metal for VVER vessel service life extension is examined. A comparative complex assessment of the degradation of VVER-440, -1000 weld-seam metal, as most subjected to radiation embrittlement due to operational factors, is presented. The main difference of the recovery annealing regimes associated with differences of their chemical composition and structural-phase state as well as the mechanisms of the degradation of the structure and properties during operation is substantiated. Comparative studies of the recovery of the structural state and mechanical properties of weld-seam metal after annealing in the chosen regimes as well as radiation embrittlement during re-irradiation were performed.

引用

页码：95 / 102

页数：8

共 19 条

[1] Mechanism of Change In VVER-440, -1000 Vessel Material Properties in Irradiation–Recovery Annealing–Irradiation Cycle
B. A. Gurovich
E. A. Kuleshova
D. A. Mal’tsev
Yu. M. Semchenkov
A. S. Frolov
Ya. I. Shtrombakh
A. V. Shutikov
Atomic Energy, 2018, 125 : 95 - 102
[2] Irradiation damage structure in VVER-440 steels after irradiation at different temperatures and post-irradiation annealing
Grosse, M
Böhmert, J
EFFECTS OF RADIATION ON MATERIALS: 19TH INTERNATIONAL SYMPOSIUM, 2000, 1366 : 323 - 342
[3] THE EFFECT OF POST-IRRADIATION ANNEALING ON VVER-440 RPV MATERIALS MECHANOLOCAL PROPERTIES AND NANO-STRUCTURE UNDER RE-IRRADIATION
Rogozkin, S.
Chernobaeva, A.
Aleev, A.
Nikitin, A.
Zaluzhnyi, A.
Erak, D.
Strombakh, Ya.
Zabusov, O.
Debarberis, L.
Zeman, A.
ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 7: OPERATIONS, APPLICATIONS AND COMPONENTS, 2010, : 553 - 562
[4] Re-embrittlement behaviour of VVER-440 reactor pressure vessel weld material after annealing
Kohopää, J
Ahlstrand, R
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2000, 77 (10) : 575 - 584
[5] Radiation embrittlement kinetics of the first generation of VVER-440 RVPs after post-irradiation annealing
Platonov, PA
Nikolaev, YA
Shtrombakh, YI
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2002, 79 (8-10) : 645 - 650
[6] Determining the irradiation temperature of witness samples of VVER-1000 AND -440 reactor vessel steel
D. Yu. Erak
V. A. Nikolaenko
Atomic Energy, 2008, 105 : 187 - 193
[7] Analysis of Mechanical Properties and Nanostructure Changes of VVER-440 Reactor Pressure Vessel Metal after Annealing
A. M. Kryukov
A. A. Chernobaeva
D. Yu. Erak
S. V. Rogozhkin
A. A. Nikitin
V. I. Lebedinsky
V. B. Papina
D. A. Zhurko
Physics of Atomic Nuclei, 2021, 84 : 1676 - 1690
[8] Analysis of Mechanical Properties and Nanostructure Changes of VVER-440 Reactor Pressure Vessel Metal after Annealing
Kryukov, A. M.
Chernobaeva, A. A.
Erak, D. Yu.
Rogozhkin, S. V.
Nikitin, A. A.
Lebedinsky, V. I.
Papina, V. B.
Zhurko, D. A.
PHYSICS OF ATOMIC NUCLEI, 2021, 84 (10) : 1676 - 1690
[9] UTILIZATION OF SPT TECHNIQUES FOR EVALUATION OF CHANGES IN THE PROPERTIES OF THE VVER-440 REACTOR PRESSURE VESSEL STEELS AFTER THEIR IRRADIATION IN THE RESEARCH AND POWER REACTORS
Brezina, Martin
Petzova, Jana
Kupca, Ludovit
Kapusnak, Michal
ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 1A, 2015,
[10] DETERMINING THE IRRADIATION TEMPERATURE OF WITNESS SAMPLES OF VVER-1000 AND-440 REACTOR VESSEL STEEL
Erak, D. Yu.
Nikolaenko, V. A.
ATOMIC ENERGY, 2008, 105 (03) : 187 - 193

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