Analysis of Mechanical Properties and Nanostructure Changes of VVER-440 Reactor Pressure Vessel Metal after Annealing

被引:1
|
作者
Kryukov, A. M. [1 ]
Chernobaeva, A. A. [2 ]
Erak, D. Yu. [2 ]
Rogozhkin, S. V. [3 ,4 ]
Nikitin, A. A. [3 ,4 ]
Lebedinsky, V. I. [1 ]
Papina, V. B. [2 ]
Zhurko, D. A. [2 ]
机构
[1] Sci & Engn Ctr Nucl & Radiat Safety, Moscow 107140, Russia
[2] Natl Res Ctr, Kurchatov Inst, Moscow 123182, Russia
[3] Natl Res Ctr, Kurchatov Inst, Alikhanov Inst Theoret & Expt Phys, Moscow 117218, Russia
[4] Natl Res Nucl Univ, MEPhI, Moscow Engn Phys Inst, Moscow 115409, Russia
关键词
reactor pressure vessel metal; radiation embrittlement; ductile-to-brittle transition temperature; atom probe tomography; clusters; ATOM-PROBE ANALYSIS; IRRADIATION; STEELS;
D O I
10.1134/S1063778821120036
中图分类号
O57 [原子核物理学、高能物理学];
学科分类号
070202 ;
摘要
Analysis of mechanical testing and microstructural investigations of the irradiated VVER-440 reactor pressure vessel (RPV) metal before and after annealing carried out in the frameworks of the international project "PRIMAVERA" is presented. The role of chemical elements (Cu and P) was studied in relation to irradiation embrittlement of the VVER-440 RPV weld metal in the initial state, after recovery annealing and after post-annealing irradiation. It was shown that under primary irradiation, copper atoms formed small clusters (size similar to 1-2 nm) which also include P, Si and Mn atoms. Phosphorus atoms also segregated on copper clusters, dislocations, grain boundaries, and additionally formed phosphorus clusters and atmospheres. Under thermal annealing at 475 degrees C, the irradiation-induced copper-enriched and phosphorus clusters partially dissolved, increasing the copper concentration in the annealed metal, which was significantly lower compared to the unirradiated material. Since most copper atoms after annealing were not contained in the ferritic matrix but in precipitates, the contribution of copper atoms to an increase in the ductile-to-brittle transition temperature under re-irradiation was minimized and so hardening and embrittlement after subsequent post-annealing irradiation were lower than under primary irradiation.
引用
收藏
页码:1676 / 1690
页数:15
相关论文
共 50 条
  • [11] 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,
  • [12] COMPARATIVE ANALYSES CONCERNING INTEGRITY OF A VVER-440 REACTOR PRESSURE-VESSEL
    SIEVERS, J
    LIU, X
    RAJAMAKI, P
    TALJA, H
    RAIKO, H
    NUCLEAR ENGINEERING AND DESIGN, 1995, 159 (01) : 63 - 68
  • [13] Comparison of microstructural features of radiation embrittlement of VVER-440 and VVER-1000 reactor pressure vessel steels
    Kuleshova, EA
    Gurovich, BA
    Shtrombakh, YI
    Erak, DY
    Lavrenchuk, OV
    JOURNAL OF NUCLEAR MATERIALS, 2002, 300 (2-3) : 127 - 140
  • [14] Study for improvement of VVER-440 reactor vessel neutron fluence calculation
    Ilieva, K
    Belousov, S
    REACTOR DOSIMETRY IN THE 21ST CENTURY, 2003, : 559 - 563
  • [15] Investigation of radiation damage in VVER-440 reactor vessel steels by SANS
    Saroun, Jan
    Kocik, Jan
    Strunz, Pavel
    PHYSICA B-CONDENSED MATTER, 2004, 350 (1-3) : E755 - E757
  • [16] Calculations of heat flowrates to the VVER-440 reactor vessel during interaction of corium melt with the reactor vessel
    Dombrovskii L.A.
    Zaichik L.I.
    Zeigarnik Yu.A.
    Mukhtarov E.S.
    Sidorov A.S.
    Thermal Engineering, 2006, 53 (04) : 302 - 306
  • [17] Pressure vessel neutron spectrum analysis of the Czech LRO/VVER-440 benchmark experiment
    Sajo, E
    Williams, ML
    Asgari, M
    Kam, FBK
    PROCEEDINGS OF THE 1996 TOPICAL MEETING RADIATION PROTECTION & SHIELDING, VOLS 1 AND 2, 1996, 1-2 : 181 - 188
  • [18] ANALYSIS OF ROD-DROP MEASUREMENTS AT A VVER-440 REACTOR
    KRELL, J
    MANGEL, B
    REBOHM, H
    NUCLEAR ENGINEERING AND DESIGN, 1995, 159 (2-3) : 265 - 271
  • [19] Radiochemical Analysis of Spent Nuclear Fuel of VVER-440 Reactor
    V. N. Momotov
    E. A. Erin
    A. Yu. Volkov
    V. N. Kupriyanov
    Radiochemistry, 2020, 62 : 629 - 638
  • [20] Radiochemical Analysis of Spent Nuclear Fuel of VVER-440 Reactor
    Momotov, V. N.
    Erin, E. A.
    Volkov, A. Yu
    Kupriyanov, V. N.
    RADIOCHEMISTRY, 2020, 62 (05) : 629 - 638