MODELING BASIC INTEGRAL CHARACTERISTICS OF POWER-PLANT WITH VVER-1000 WATER-COOLED POWER-REACTOR OPERATING IN FLEXIBLE MODE (FOCUS MODEL)

被引：0

作者：

ANIKANOV, SS

ANDRONOV, YI

机构：

来源：

ATOMIC ENERGY | 1993年 / 74卷 / 05期

关键词：

D O I：

10.1007/BF00844618

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：

[No abstract available]

引用

页码：345 / 347

页数：3

共 12 条

[1] The method of control of nuclear power plant with VVER-1000 reactor in maneuverable mode
Maksimov, M.V.
Tsiselskaya, T.A.
Kokol, E.A.
Journal of Automation and Information Sciences, 2015, 47 (06) : 17 - 32
[2] STATE OF ART AND PROSPECTS FOR DEVELOPMENT OF TECHNOLOGY OF ATOMIC POWER-PLANTS POWERED BY WATER-MODERATED WATER-COOLED REACTOR VVER-1000
ZOREV, NN
SOVIET ATOMIC ENERGY, 1977, 42 (04): : 326 - 333
[3] INVESTIGATING THE STEAM GENERATORS OF THE MAIN UNIT ON A NUCLEAR POWER STATION (AES) WITH A WATER-MODERATED WATER-COOLED VVER-1000 REACTOR.
Tarankov, G.A.
Titov, V.F.
Logvinov, S.A.
Kozlov, Yu.V.
Nekrasov, A.V.
Pikus, V.Yu.
Dmitriev, A.I.
Galetskii, N.S.
Ilyushin, V.F.
Sitnik, Yu.K.
Soviet Energy Technology (English translation of Energomashinostroenie), 1986, (05): : 54 - 58
[4] APPARATUS FOR THE INVESTIGATION OF CRACKING OF MATERIALS IN THIN-WALLED ELEMENTS IN THE CORE OF A WATER-MODERATED, WATER-COOLED POWER-REACTOR (VVER)
VAINER, LA
KOZHEVNIKOV, OA
SHOKA, IV
SOVIET ATOMIC ENERGY, 1989, 66 (04): : 306 - 309
[5] THE RESULTS OF TESTING AN ELECTROMAGNETIC FILTER IN THE SECONDARY LOOP OF A NUCLEAR-POWER STATION WITH A WATER-MODERATED WATER-COOLED VVER-440 POWER-REACTOR
TSYRULNIKOV, DL
YURCHEVSKII, EB
BELAN, FI
MAMET, AP
YARICHIN, AD
LABAZNIKOV, SV
TSYBULNIK, LP
NOVIKOV, MV
BEREZKIN, NN
THERMAL ENGINEERING, 1987, 34 (04) : 188 - 191
[6] EXPERIENCE IN MANAGEMENT AND IMPROVEMENT OF THE WATER-CHEMICAL REGIME IN THE SECONDARY CIRCUIT OF THE VVER-1000 OF THE KALININ ATOMIC POWER-PLANT
NOEV, VV
KUKHAREV, ND
OTCHENASHEV, GD
GUZEEVA, GI
KOCHETOVA, GG
SOVIET ATOMIC ENERGY, 1991, 71 (05): : 892 - 901
[7] DISTRIBUTION OF CORROSION PRODUCTS IN THE STEAM-AND-WATER CIRCUIT OF A POWER-GENERATING UNIT WITH WATER-MODERATED WATER-COOLED VVER-1000 REACTOR DURING HYDRAZINE WATER-TREATMENT
BYKOVA, VV
ERPYLEVA, SF
MAMET, VA
TYAPKOV, VF
THERMAL ENGINEERING, 1991, 38 (07) : 356 - 359
[8] Simulation of thermal breakdown of a reactor vessel as a result of a heavy accident in a nuclear power plant with reactors of VVER (water-moderated water-cooled power reactor) type
Dolgov, VV
Kashcheev, MV
Muranov, YV
HIGH TEMPERATURE, 1996, 34 (05) : 759 - 769
[9] Simulation of Thermal Breakdown of a Reactor Vessel as a Result of Heavy Accident in a Nuclear Power Plant with Reactors of VVER (Water-moderated Water-cooled Power Reactor) Type
Dolgov, V. V.
Kashcheev, M. V.
Muranov, Y. V.
High Temperature (English translation of Teplofizika Vysokikh Temperatur), 1996, 34 (05):
[10] An investigation of burnout on the downward facing slope surfaces of the water-cooled components of a corium localizing device at a nuclear power station with VVER-1000 reactors
Efimov, V.K., 2001, Maik Nauka

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