Separation of gaseous fission products from reactor and reprocessing-plant off-gases

1978 ◽  
Vol 12 (1) ◽  
pp. 85-88 ◽  
Author(s):  
S. G. Mastera ◽  
M. Laser ◽  
E. Merz
2021 ◽  
Vol 7 (4) ◽  
pp. 319-325
Author(s):  
Anastasiya V. Dragunova ◽  
Mikhail S. Morkin ◽  
Vladimir V. Perevezentsev

To timely detect failed fuel elements, a reactor plant should be equipped with a fuel cladding tightness monitoring system (FCTMS). In reactors using a heavy liquid-metal coolant (HLMC), the most efficient way to monitor the fuel cladding tightness is by detecting gaseous fission products (GFP). The article describes the basic principles of constructing a FCTMS in liquid-metal-cooled reactors based on the detection of fission products and delayed neutrons. It is noted that in a reactor plant using a HLMC the fuel cladding tightness is the most efficiently monitored by detecting GFPs. The authors analyze various aspects of the behavior of fission products in a liquid-metal-cooled reactor, such as the movement of GFPs in dissolved and bubble form along the circuit, the sorption of volatile FPs in the lead coolant (LC) and on the surfaces of structural elements, degassing of the GFPs dissolved in the LC, and filtration of cover gas from aerosol particles of different nature. In addition, a general description is given of the conditions for the transfer of GFPs in a LC environment of the reactor being developed. Finally, a mathematical model is presented that makes it possible to determine the calculated activity of reference radionuclides in each reactor unit at any time after the fuel element tightness failure. Based on this model, methods for monitoring the fuel cladding tightness by the gas activity in the gas volumes of the reactor plant will be proposed.


Author(s):  
Yoshinobu Nakamura ◽  
Shizuka Suda ◽  
Koich Ishiyama ◽  
Masaru Watahiki ◽  
Hideyo Mutoh

Abstract Volume of nitric acid solution, which contain the most of fission products (FPs), is concentrated to 0.5–2m3 in an HALW evaporator by reprocessing a spent fuel of ltU. The HALW is stored in HALW storage tanks temporarily till it is transferred to the Tokai Vitrification Facility (TVF). During the storage, the HALW of 1–8m3/y vaporized per storage tank. A shift coefficient of radioactive nuclides from the HALW to off-gas was 4E−11. Through the operation experience, knowledge obtained about storage management of highly active liquid waste (HALW) is reported.


1998 ◽  
Vol 233 (1-2) ◽  
pp. 281-284 ◽  
Author(s):  
C. Chung ◽  
C. Y. Chen ◽  
C. S. Lin ◽  
W. W. Yeh ◽  
C. J. Lee

Author(s):  
Pavel N. Alekseev ◽  
Alexander A. Proshkin ◽  
Alexander L. Shimkevich

In developing methods for designing reactor materials with reference to nuclear fuel, a task for micro-structural suppressing the processes of swelling, corrosion, and forming macroscopic defects (phase inclusions, pores, gaseous bubbles, cracks) in the fuel is formulated. For managing the defective structure of materials under irradiation, it is offered to choose their composition that fuel oxide ceramics have consisted of steady-state fractal tetrahedral clusters as the dense part of amorphous matrix (the nano-ceramic structure). In this connection, the search of multi-component systems providing this stable state can become a perspective direction for designing fuel with small swelling and corrosion factor. Such the materials will have high density of equilibrium vacancies that effectively absorb solid and gaseous fission products, and reduce the fuel swelling factor, physical, chemical, and thermal properties.


1969 ◽  
Vol 125 (2) ◽  
pp. 267-275 ◽  
Author(s):  
G.C. Carlson ◽  
W.C. Schick ◽  
W.L. Talbert ◽  
F.K. Wohn

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