Gas-phase composition in the fuel rods at Novyi Voronezh nuclear power station

1976 ◽  
Vol 40 (3) ◽  
pp. 243-246 ◽  
Author(s):  
A. T. Ageenkov ◽  
A. A. Buravtsov ◽  
E. M. Valuev ◽  
L. I. Golubev ◽  
Z. V. Ershova ◽  
...  
Author(s):  
Huaibin Li ◽  
Yaru Fu ◽  
Lanfang Mao ◽  
Qiliang Mei

When fuel rods have defects, the fission products in the fuel rods will come out and enter the reactor coolant through the defects. The release of the fission products will result in the increase of radiation dose, the indeterminacy of the fuel management and will influence the economics and safety of the nuclear power station. Based on the analysis of the typical nuclides activities in reactor coolant, the evaluation of the defect fuel rods can be realized. This paper studied the related analysis around the world and determined the methods to evaluate the number, the defect type (open or tight) and the burn-up of the defect fuel rods. The evaluation method of this paper can be used to evaluate the defects of fuel rods, and can provide valuable information for the fuel management and dose analysis, and also can be a useful technical support to the operation of nuclear power station.


Author(s):  
Norio Sakai ◽  
Hideki Horie ◽  
Hiromasa Yanagisawa ◽  
Tadashi Fujii ◽  
Shinya Mizokami ◽  
...  

A phenomena identification ranking table (PIRT) was constructed to identify important phenomena that should be considered in simulating the accident progression for the Fukushima Dai-ichi nuclear power station and predicting the molten core and debris distribution in the reactor system with the MAAP code. The accident scenario, starting from reactor scram to PCV failure, was divided into four time phases in which fuel rod degradation, molten core relocation, and reactor vessel failure were selected as the phase-changing events. Phenomena that would have occurred in the accident were identified in the plant system including the reactor vessel and the containment that consist of 16 sub-components, consistent with the MAAP nodalization for the BWR system. The importance of the identified phenomena was evaluated for each time phase in cooperation with the experts in the Atomic Energy Society of Japan. Eventually total of 1047 phenomena were identified, of which 386 were ranked as ‘highly’ important for the analysis code to evaluate the behavior of molten fuel rods and reactor internal materials. These important phenomena are compared with those considered in the current MAAP analysis models to make sure what should be enhanced to improve the analysis capability for the accident progression.


1980 ◽  
Vol 48 (6) ◽  
pp. 409-413 ◽  
Author(s):  
V. M. Sedov ◽  
P. G. Krutikov ◽  
E. A. Konstantinov ◽  
V. A. Shishkunov ◽  
A. A. Afanas'ev

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