Possibility analysis of corium confinement in the WWER-640 vessel after severe accidents with core disruption

被引：0

作者：

Rogov, M.F. ^{[1
]}

Logvinov, S.A. ^{[1
]}

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

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

Khabenskij, V.B. ^{[1
]}

Bezlepkin, V.V. ^{[1
]}

Kukhtevich, I.V. ^{[1
]}

机构：

[1] OKB 'Gidropress', Podol'sk, Russia

来源：

Teploenergetika | 1996年 / 11期

关键词：

D O I：

暂无

中图分类号：

学科分类号：

摘要：

引用

页码：12 / 15

共 7 条

[1] Estimation of possibility of corium melt confinement in the WWER-640 reactor vessel
At Energ, 5 (380-386):
[2] Safety conception for conditions of severe accidents of NPP with the WWER-640 reactor
Bezlepkin, V.V.
Gorbaev, V.A.
Molchanov, A.V.
Ivanov, V.K.
Granovskij, V.S.
Karaseva, M.A.
Ermolaev, V.F.
Teploenergetika, 1995, (12): : 13 - 18
[3] Analyzing the possibility of retaining the corium in the vessel of a VVER-640 reactor in a severe accident with a damaged core
Rogov, M.F.
Logvinov, S.A.
Granovskii, V.S.
Kovtunova, S.V.
Khabenskii, V.B.
Bezlepkin, V.V.
Kukhtevich, I.V.
Thermal Engineering (English translation of Teploenergetika), 43 (11):
[4] DESIGN ANALYSIS OF CORIUM IMMOBILIZATION AND COOLING OF THE REACTOR VESSEL IN SEVERE ACCIDENTS AT NPP WITH COMMERCIAL UNIT V-320
Stremedlovskyi, Roman A.
PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 6, 2014,
[5] Design Analysis of the Molten Core Confinement within the Reactor Vessel in the Case of Severe Accidents at Nuclear Power Plants Equipped with a Reactor of the VVER Type
Zvonaryov, Yu. A.
Budaev, M. A.
Volchek, A. M.
Gorbaev, V. A.
Zagryazkin, V. N.
Kiselyov, N. P.
Kobzar', V. L.
Konobeev, A. V.
Tsurikov, D. F.
PHYSICS OF ATOMIC NUCLEI, 2013, 76 (14) : 1688 - 1699
[6] Design analysis of the molten core confinement within the reactor vessel in the case of severe accidents at nuclear power plants equipped with a reactor of the VVER type
Yu. A. Zvonaryov
M. A. Budaev
A. M. Volchek
V. A. Gorbaev
V. N. Zagryazkin
N. P. Kiselyov
V. L. Kobzar’
A. V. Konobeev
D. F. Tsurikov
Physics of Atomic Nuclei, 2013, 76 : 1688 - 1699
[7] Sensitivity Analysis of Ex-Vessel Corium Coolability Models in MAAP5 Code for the Prediction of Molten Corium-Concrete Interaction after a Severe Accident Scenario
Amidu, Muritala Alade
Addad, Yacine
Hidaka, Akihide
ENERGIES, 2022, 15 (15)

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