Monitoring of mechanical properties of vessel materials of water-moderated water-cooled reactors of nuclear power plants for assurance of their safe service

被引：0

作者：

Amaev, AD ^{[1
]}

Korolev, YN ^{[1
]}

Krasikov, EA ^{[1
]}

Shtrombakh, YI ^{[1
]}

机构：

[1] Kurchatov Inst, Russian Sci Ctr, Moscow, Russia

来源：

INDUSTRIAL LABORATORY | 2000年 / 66卷 / 07期

关键词：

D O I：

10.1023/A:1004162530861

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

Methods to monitor the mechanical properties of the material of reactor vessels with a view to ensuring their safe service are presented. Data on the hydrogen and radiation resistance of vessels unclad with stainless steel for protection are discussed. A method using small-size substandard impact-test specimens for determination of the critical brittle point for in-service reactor vessels is substantiated. A scheme for predicting the radiation life of reactor vessels treated by recovery annealing technology to enhance their safe service is proposed.

引用

页码：462 / 470

页数：9

共 50 条

[1] PROSPECTS OF WATER-MODERATED WATER-COOLED POWER REACTORS
SKVORTSO.SA
SOVIET ATOMIC ENERGY-USSR, 1970, 28 (04): : 380 - &
[2] DEVELOPMENT OF NUCLEAR-POWER PLANTS WITH WATER-MODERATED WATER-COOLED REACTORS IN SOVIET-UNION
DENISOV, VP
MARKOV, JV
SIDORENK.VA
SKVORCOV, SA
STEKOLNI.VV
VORONIN, LM
KERNENERGIE, 1972, 15 (11-1): : 361 - 369
[3] NUCLEAR-POWER-PLANTS WITH WATER-MODERATED WATER-COOLED REACTORS IN POWER-SYSTEMS - ADAPTATION METHODS
KHRUSTALEV, VA
SOVIET ATOMIC ENERGY, 1991, 71 (06): : 1013 - 1017
[4] SOME SAFETY PROBLEMS IN NUCLEAR-POWER PLANTS WITH WATER-COOLED WATER-MODERATED POWER-REACTORS
OSTASHEN.VF
BUMBLIS, II
ALPATOV, AM
SOVIET ATOMIC ENERGY-USSR, 1971, 30 (02): : 152 - &
[5] APPLICATION OF THE SYSTEM OF AUTOMATED MONITORING OF THE RESIDUAL SERVICE LIFE FOR THE SOLUTION OF THE PROBLEMS OF OPERATION OF NUCLEAR POWER PLANTS WITH WATER-COOLED WATER-MODERATED REACTORS
Berkovich, V. Ya.
Bogachev, A. V.
Dranchenko, B. N.
Semishkin, V. P.
STRENGTH OF MATERIALS, 2010, 42 (01) : 44 - 50
[6] Application of the system of automated monitoring of the residual service life for the solution of the problems of operation of nuclear power plants with water-cooled water-moderated reactors
V. Ya. Berkovich
A. V. Bogachev
B. N. Dranchenko
V. P. Semishkin
Strength of Materials, 2010, 42 : 44 - 50
[7] DECONTAMINATION OF EQUIPMENT OF NUCLEAR-POWER STATIONS WITH WATER-MODERATED WATER-COOLED REACTORS
BALABANIRMENIN, YV
TEPLITSKII, AL
MATSKEVICH, GV
NETESIN, VB
TEPLOV, PV
LUCHKIN, VG
THERMAL ENGINEERING, 1983, 30 (12) : 691 - 692
[8] STATUS AND DEVELOPMENT OUTLOOK OF NUCLEAR POWER STATIONS WITH WATER-COOLED WATER-MODERATED REACTORS
SKVORTSO.SA
SOVIET ATOMIC ENERGY, 1968, 25 (04): : 1140 - &
[9] Thermal and radiation characteristics of hydrazine in the primary loop of nuclear power plants with water-cooled, water-moderated reactors
Arkhipov, OP
Bugaenko, VL
Kabakchi, SA
Pashevich, VI
ATOMIC ENERGY, 1997, 82 (02) : 92 - 98
[10] Thermal and radiation characteristics of hydrazine in the primary loop of nuclear power plants with water-cooled, water-moderated reactors
O. P. Arkhipov
V. L. Bugaenko
S. A. Kabakchi
V. I. Pashevich
Atomic Energy, 1997, 82 : 92 - 98

← 1 2 3 4 5 →