A method of calculating the leakage of first-loop coolant into the boiler water in modified steam generators in power stations containing VVER-1000 reactors

被引：0

作者：

Pyrkov, IV

Ivanov, EA

Kham'yanov, LP

机构：

来源：

ATOMIC ENERGY | 1997年 / 83卷 / 04期

关键词：

Steam; Boiler Water; Steam Generator; Modify Steam Generator; Modify Steam;

D O I：

10.1007/BF02414117

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：775 / 778

页数：4

共 22 条

[1] A method of calculating the leakage of first-loop coolant into the boiler water in modified steam generators in power stations containing VVÉR-1000 reactors
I. V. Pyrkov
E. A. Ivanov
L. P. Kham'yanov
Atomic Energy, 1997, 83 : 775 - 778
[2] METHOD FOR DIAGNOSTICS OF COOLANT LEAKS IN THE FIRST LOOP INTO THE BOILER WATER OF STEAM-GENERATORS IN NUCLEAR-POWER-PLANTS WITH VVER-440 AND VVER-1000 REACTORS
IVANOV, EA
PYRKOV, IV
KHAMYANOV, LP
ATOMIC ENERGY, 1994, 77 (01) : 543 - 548
[3] SNESK PROGRAM FOR CALCULATING FIRST-LOOP COOLANT LEAKS INTO THE BOILER WATER OF THE STEAM-GENERATORS OF A NUCLEAR-POWER-PLANT WITH A VVER REACTOR
IVANOV, EA
PYRKOV, IV
KHAMYANOV, LP
ATOMIC ENERGY, 1994, 77 (06) : 944 - 945
[4] Experience with chemical washing of steam generators in the course of scheduled maintenance at nuclear power stations with VVER-1000 reactors
Brykov, S.I.
Arkhipov, O.P.
Siryapina, L.A.
Mamet, V.A.
Thermal Engineering, 1999, 46 (06): : 459 - 462
[5] MODEL OF ACCUMULATION OF RADIONUCLIDES IN BOILER WATER OF STEAM-GENERATORS IN NUCLEAR-PLANTS WITH VVER-440 AND VVER-1000 REACTORS
IVANOV, EA
PYRKOV, IV
KHAMYANOV, LP
ATOMIC ENERGY, 1994, 77 (01) : 549 - 553
[6] Criteria for plugging heat-transfer tubes in steam generators at nuclear power stations with VVER-440 and VVER-1000 reactors
Teploenergetika, 1998, 45 (02): : 161 - 163
[7] Method for calculation of a first circuit coolant leakage into the boiler water of reconstructed steam generators of NPP with WWER-1000
Pyrkov, I.V.
Ivanov, E.A.
Kham'yanov, L.P.
Atomnaya Energiya, 1997, 83 (04): : 310 - 312
[8] SOME OF THE PROBLEMS INVOLVED IN IMPROVING OPERATIONAL RELIABILITY OF THE WATER LEVEL CONTROLLER IN STEAM-GENERATORS ON NUCLEAR-POWER STATIONS WITH VVER-1000 REACTORS
VYSOTSKII, VG
DAVIDENKO, NN
THERMAL ENGINEERING, 1991, 38 (09) : 482 - 485
[9] STEAM-GENERATORS OF THE POWER-GENERATING UNITS OF NUCLEAR-POWER-PLANTS WITH VVER-1000 REACTORS
TITOV, VF
ATOMIC ENERGY, 1994, 77 (02) : 588 - 595
[10] DAMAGE TO THE OUTPUT MANIFOLDS OF STEAM-GENERATORS AT NUCLEAR-POWER-PLANTS WITH VVER-1000 REACTORS
BARANENKO, VI
KIROV, VS
KRAVCHENKO, VP
KOROVKIN, VA
FRIDMAN, NA
ATOMIC ENERGY, 1993, 75 (05) : 896 - 899

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