Studying Helium Accumulation in Austenitic Steels for Evaluating Radiation Damage in Internals of Water-Moderated Water-Cooled Power Reactors

被引：6

作者：

Belozerov, S. V. ^{[1
]}

Neustroyev, V. S. ^{[1
]}

Shamardin, V. K. ^{[1
]}

机构：

[1] Res Inst Atom Reactors FGUP GNTs RF NIIAR, Dimitrovgrad 433510, Ulyanovsk Oblas, Russia

来源：

PHYSICS OF METALS AND METALLOGRAPHY | 2008年 / 106卷 / 05期

关键词：

61.82.Bg; 81.40.Wk;

D O I：

10.1134/S0031918X08110100

中图分类号：

TF [冶金工业];

学科分类号：

0806 ;

摘要：

The accumulation of helium in austenitic steels upon the irradiation in research and power reactors has been studied. It has been shown that the application of a high-sensitive mass-spectrometric method of determining integral accumulation of helium makes it possible to obtain reliable correlation dependences between the content of helium in the irradiated steel and the damaging dose.

引用

页码：503 / 509

页数：7

共 50 条

[41] DAMAGE TO HEAT-EXCHANGER TUBES IN STEAM-GENERATORS ON NUCLEAR-POWER STATIONS WITH WATER-MODERATED WATER-COOLED REACTORS
TITOV, VF
BANYUK, GF
BRYKOV, SI
THERMAL ENGINEERING, 1992, 39 (03) : 61 - 63
[42] PROBLEM OF RELIABILITY OF STEAM-GENERATORS AT NUCLEAR-POWER STATIONS WITH WATER-MODERATED WATER-COOLED REACTORS
STYRIKOVICH, MA
MARGULOVA, TK
THERMAL ENGINEERING, 1974, 21 (09) : 76 - 79
[43] SOVIET-FRENCH SEMINAR ON SAFETY OF ATOMIC POWER-PLANTS WITH WATER-MODERATED WATER-COOLED REACTORS
ISAEV, AN
SOVIET ATOMIC ENERGY, 1979, 46 (05): : 424 - 426
[44] A phenomenological method for determining mechanical properties of the vessel steels of water-moderated water-cooled power reactors (WWPR) from the ball indentation diagram
Bakirov, MB
Potapov, VN
INDUSTRIAL LABORATORY, 2000, 66 (12): : 803 - 811
[45] The First Water-Cooled Water-Moderated Critical Assemblies in the USSR
G. A. Gladkov
Yu. V. Nikol'skii
Atomic Energy, 2001, 90 : 100 - 102
[46] PERIODIC INSPECTION OF STATE OF METAL MAKING UP VESSEL OF WATER-MODERATED WATER-COOLED REACTORS
OVCHINNIKOV, FY
SEDOV, VK
SERGUNOV, VT
KRUGLOV, VP
ZLEPKO, VF
KALININ, VP
DEGTYANNIKOV, YF
SOVIET JOURNAL OF NONDESTRUCTIVE TESTING-USSR, 1977, 13 (03): : 301 - 307
[47] RADIOCHEMICAL INVESTIGATIONS OF THE COMPOSITION OF SPENT FUEL FROM WATER-COOLED WATER-MODERATED REACTORS (VVER)
STEPANOV, AV
MAKAROVA, TP
LIPOVSKII, AA
AKOPOV, GA
BIBICHEV, BA
LOVTSYUS, AV
NIKITINA, SA
PREOBRAZHENSKAYA, LD
BELYAEV, BN
RYZHINSKII, MV
FRIDKIN, AM
SOVIET RADIOCHEMISTRY, 1982, 24 (05): : 547 - 554
[48] VTI NOMOGRAMS FOR CALCULATING THE PH OF COOLANT IN THE PRIMARY LOOP OF WATER-MODERATED WATER-COOLED REACTORS
SHEININ, RA
GOLDSHTEIN, II
SIROTA, AM
THERMAL ENGINEERING, 1981, 28 (08) : 489 - 491
[49] The first water-cooled water-moderated critical assemblies in the USSR
Gladkov, GA
Nikol'skii, YV
ATOMIC ENERGY, 2001, 90 (02) : 100 - 102
[50] IMPROVING THE CLEANING OF BLOWDOWN WATER OF THE STEAM-GENERATORS OF NUCLEAR-POWER STATIONS WITH WATER-MODERATED WATER-COOLED REACTORS
SIRYAPINA, LA
MARGULOVA, TK
THERMAL ENGINEERING, 1985, 32 (04) : 226 - 227

← 1 2 3 4 5 →