Experimental Study on the Behavior of Suspended Aerosols of Sodium and Nonradioactive Fission Products (SrO2and CeO2) in a Closed Vessel

2011 ◽  
Vol 176 (1) ◽  
pp. 83-92 ◽  
Author(s):  
V. Subramanian ◽  
R. Baskaran ◽  
J. Misra ◽  
R. Indira
Fuel ◽  
2019 ◽  
Vol 248 ◽  
pp. 232-240 ◽  
Author(s):  
Yuying Chen ◽  
Qi Zhang ◽  
Mingzhi Li ◽  
Mengqi Yuan ◽  
Dejian Wu ◽  
...  

Author(s):  
M. Gouëllo ◽  
J. Kalilainen ◽  
P. Rantanen ◽  
T. Kärkelä ◽  
A. Auvinen

In case of a severe accident in a light water reactor, iodine is one of the most important fission products in the context of reactor safety because of its significant total fuel inventory, high specific activity and radiotoxicity. Consequently, understanding its behavior under severe accident transient conditions is a major point in the optimization of the accident management and mitigation. An experimental study has been launched at VTT investigating the behavior of iodine on primary circuit surfaces during a severe nuclear accident. The paper presents results obtained from the heating of metallic cadmium and caesium iodide in a crucible at temperature below 400°C under three different atmospheres. Aerosols and gaseous species released from the reaction crucible were sampled at 150°C on filters and liquid scrubbers and analyzed with HR-ICP-MS. At first, experiments were conducted with one precursor (cadmium or caesium iodide). It was observed that cadmium is predominantly present as aerosol in all atmospheres but represents less than 1% of mass what has been recovered from the facility leaching. To the contrary, caesium iodide experiment showed that sampled iodine exists mainly as gaseous species. By comparison to one-precursor studies, a change in the behavior of element was noticed when cadmium was added to caesium iodide. Different observations let to suggest a reaction between caesium iodide and cadmium in the crucible. The reaction would lead to the formation of compound made of cadmium and iodine in condensed phase below 150°C. More gaseous iodine was found from the sampling line with Ar/H2O/H2 atmosphere than in Ar/H2O atmosphere, suggesting that the cadmium is more reactive toward iodine in hydrogen-free atmosphere.


1990 ◽  
Vol 221 ◽  
pp. 383-409 ◽  
Author(s):  
S. Douady

An experimental study of surface waves parametrically excited by vertical vibrations is presented. The shape of the eigenmodes in a closed vessel, and the importance of the free-surface boundary conditions, are discussed. Stability boundaries, wave amplitude, and perturbation characteristic time of decay are measured and found to be in agreement with an amplitude equation derived by symmetry. The measurement of the amplitude equation coefficients explains why the observed transition is always supercritical, and shows the effect of the edge constraint on the dissipation and eigen frequency of the various modes. The fluid surface tension is obtained from the dispersion relation measurement. Several visualization methods in large-aspect-ratio cells are presented.


Author(s):  
Anatoly Bushuev ◽  
Yury Verzilov ◽  
Victor Zubarev ◽  
Tatiana Aleeva ◽  
Ekaterina Petrova ◽  
...  

Abstract The paper is devoted to investigations of spent reactor graphite contamination. The study was based on the sampling from the graphite stacks and sleeves of three shut down plutonium-production reactors in Siberian Group of Chemical Enterprises (SGCE), Seversk (Tomsk-7). Several hundreds graphite samples were analysed by means of α-, β-, γ- and X-ray spectrometry. Contents of 3H, 14C, fission products, actinides, products of impurities neutron activation were determined. The inventories of above mentioned radionuclides were estimated. Correlation between content of various groups of radionuclides was studied. Graphite sleeves contamination was studied depending on the period of their irradiation. Comparison of obtained experimental data for the three SGCE reactors with calculated predictions showed substantial difference. The conclusion was made on applicability of the data obtained for estimations of spent graphite contamination in other reactor types including RBMK reactors. The main part of the studies was performed in the frame of the ISTC Projects No. 561 and No. 1409 fulfilment.


Fuel ◽  
2021 ◽  
Vol 285 ◽  
pp. 119222
Author(s):  
Xiaozhe Yu ◽  
Jianliang Yu ◽  
Chenyang Wang ◽  
Xianshu Lv ◽  
Yalei Wang ◽  
...  

1981 ◽  
Vol 18 (1) ◽  
pp. 1695-1702 ◽  
Author(s):  
Andrew A. Adamczyk ◽  
E.W. Kaiser ◽  
J.A. Cavolowsky ◽  
G.A. Lavoie

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