Calculation and experimental investigation of the heat removal modes of a shutdown BN-600 reactor of the beloyarsk nuclear power station

1985 ◽  
Vol 59 (1) ◽  
pp. 613-615
Author(s):  
A. I. Karpenko ◽  
A. A. Lyzhin ◽  
A. G. Sheinkman
Keyword(s):  
Experimental Investigation ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Heat Removal ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station

In-plane bending of a large 90° smooth bend

1966 ◽  
Vol 1 (4) ◽  
pp. 290-300 ◽  
Author(s):  
G E Findlay ◽  
J Spence
Keyword(s):  
Experimental Investigation ◽  
Asymptotic Solution ◽  
Nuclear Power Station ◽  
Excellent Agreement ◽  
Nuclear Power ◽  
Reactor Vessel ◽  
Power Station ◽  
Plane Bending ◽  
Extensive Computation

An experimental investigation has been conducted on a 6 ft 6 in diameter 90° smooth bend which forms part of the outlet ducting of Number 2 reactor vessel at Sizewell nuclear power station. The results of the investigation show excellent agreement with various available theories, both for stresses and flexibility factors. The theories themselves are discussed and it is concluded that the asymptotic solution of Clark and Reissner, largely neglected in this country, has distinct advantages in many cases, being relatively simple to use and giving comparable results with other theories which require extensive computation.

Developing neutron-flux control algorithms for the reactor in the second unit at the Beloyarsk nuclear power station

1986 ◽  
Vol 60 (5) ◽  
pp. 359-363
Author(s):  
E. V. Filipchuk ◽  
P. T. Potapenko ◽  
O. L. Bozhenkov ◽  
O. M. Saraev ◽  
N. G. Gladkov ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Control Algorithms ◽  
Power Station ◽  
Flux Control ◽  
Beloyarsk Nuclear Power Station

Fuel-channel power monitoring system for the reactor used in the second unit of the beloyarsk nuclear power station

1974 ◽  
Vol 36 (3) ◽  
pp. 215-218 ◽  
Author(s):  
B. G. Dubovskii ◽  
A. Ya. Evseev ◽  
V. V. Ezhov ◽  
V. A. Zagadkin ◽  
V. F. Lyubchenko ◽  
...  
Keyword(s):  
Nuclear Power Station ◽  
Monitoring System ◽  
Nuclear Power ◽  
Power Station ◽  
Channel Power ◽  
Power Monitoring ◽  
Fuel Channel ◽  
Beloyarsk Nuclear Power Station

Operative monitoring system for the energy-liberation fields of the reactors in the Beloyarsk nuclear-power station

1976 ◽  
Vol 40 (2) ◽  
pp. 174-177
Author(s):  
N. Ya. Kulikov ◽  
�. I. Snitko ◽  
A. M. Rasputnis ◽  
V. P. Solodov
Keyword(s):  
Nuclear Power Station ◽  
Monitoring System ◽  
Nuclear Power ◽  
Energy Liberation ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station ◽  
Operative Monitoring

Cooling conditions of the reactor of the Beloyarsk nuclear power station first unit during shutdown of the station and depressurization of the evaporative circuit

1983 ◽  
Vol 54 (2) ◽  
pp. 103-106 ◽  
Author(s):  
P. A. Gavrilov ◽  
V. G. Zakharov ◽  
G. A. Zvereva ◽  
A. I. Ionov ◽  
V. D. Kozyrev ◽  
...  
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station ◽  
Cooling Conditions

Tests on zirconium superheating channels in the first unit at the Kurchatov Beloyarsk nuclear power station

1979 ◽  
Vol 46 (1) ◽  
pp. 58-60 ◽  
Author(s):  
A. N. Grigor'yants ◽  
B. B. Baturov ◽  
V. M. Malyshev ◽  
S. V. Shirokov ◽  
V. I. Mikhan
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station

Operating experience with the beloyarsk nuclear power station

1969 ◽  
Vol 27 (5) ◽  
pp. 1153-1161 ◽  
Author(s):  
N. A. Dollezhal' ◽  
P. I. Aleshchenkov ◽  
Yu. V. Evdokimov ◽  
I. Ya. Emel'yanov ◽  
B. G. Ivanov ◽  
...  
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Operating Experience ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station

Long-Term Cooling Strategy for the Primary Containment Vessel of the Kashiwazaki-Kariwa Nuclear Power Station in a Severe Accident

2017 ◽  
Author(s):  
Satoshi Kawaguchi ◽  
Satoshi Mizuno ◽  
Yoshihiro Oyama
Keyword(s):  
Heat Exchanger ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Heat Removal ◽  
Severe Accident ◽  
Power Station ◽  
Working Temperature ◽  
Containment Vessel ◽  
Portable Pump

This paper explains the strategy of our company (Tokyo Electric Power, TEPCO) regarding means of long-term heat removal from the primary containment vessel (PCV) of Units 6 and 7 (ABWR) of the Kashiwazaki-Kariwa Nuclear Power Station in a severe accident. If the PCV continues in a high-temperature state for a long time, the strength of the PCV concrete will decline, and the risk of being affected by an earthquake will increase. Therefore, it is crucial for safety to cool the PCV and reduce its temperature to the maximum working temperature or lower. TEPCO provides a means of cooling the reactor pressure vessel (RPV) and PCV called the alternative coolant circulation system (ACCS). This system uses the heat exchanger of the residual heat removal (RHR) system, the make up water condensate (MUWC) pump, and alternative heat exchanger vehicles. By using these measures, it is possible reduce temperature in the PCV over the long term to the maximum working temperature (design value) or less, even in severe accident scenarios such as a large LOCA + ECCS function failures + SBO (station blackout). This function has quite high reliability, but in a scenario where these measures cannot be used, expectations are placed on the filtered vent (FV). However, due to FV characteristics, it is impossible to reduce to below the saturation temperature of 100°C at atmospheric pressure using FV alone, and it will be necessary in the medium/long-term to cool the PCV while also restoring the cooling equipment. Therefore, the following restoration operation of PCV cooling and its dose evaluation were studied. (1) RPV heat removal by restoring the RHR system (2) RPV and PCV heat removal using a portable pump employing a portable heat exchanger (3) RPV and PCV heat removal using the suppression pool water clean up system (SPCU) employing portable heat exchangers (4) RPV heat removal using the clean up water system (CUW) By clarifying beforehand issues such as feasibility of these systems, the on-site environment for restoration measures, and the necessary gear/systems, the authors were able to secure means of long-term cooling of the PCV, and further enhance PCV reliability.

Steam effects and reactivity coefficients of the beloyarsk nuclear power station reactors

1981 ◽  
Vol 50 (6) ◽  
pp. 338-342 ◽  
Author(s):  
V. P. Andreev ◽  
A. V. Bondarenko ◽  
V. K. Vikulov ◽  
V. D. Kozyrev ◽  
F. M. Krasnogorov ◽  
...  
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station ◽  
Reactivity Coefficients

The Beloyarsk nuclear power station turns 45

2009 ◽  
Vol 56 (11) ◽  
pp. 977-978
Author(s):  
R. I. Toporkov ◽  
V. N. Koinov
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station
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