Experience on wet storage spent fuel sipping at IEA-R1 Brazilian research reactor

1998 ◽  
Vol 25 (4-5) ◽  
pp. 237-258 ◽  
Author(s):  
J.A. Perrotta ◽  
L.A.A. Terremoto ◽  
C.A. Zeituni
2008 ◽  
Vol 59 (2) ◽  
pp. 178-180
Author(s):  
Cristina Ciuculescu ◽  
Tanase Dobre

The paper presents the results obtained from the curves curent-potential when Al-Mg3 samples polarization occurs in solutions that simulate the water from the storage pool. The samples used in research are characteristic for the fuel spent C-36 and EK-10 and also for the storage pool from the Magurele- Romania research reactor deactivation. The study is unique due to the material samples used and due to the fact that the results of electrochemical experiments are correlated to the results from the chemical analysis of water samples from spent fuel storage basins. The paper is in the class of those which serve to the estimation of the dynamics of the degradation of spent fuel cladding during wet storage.


2005 ◽  
Vol 20 (2) ◽  
pp. 45-60 ◽  
Author(s):  
Milan Pesic ◽  
Tatjana Maksin ◽  
Gabrijela Jordanov ◽  
Rajko Dobrijevic ◽  
Zoja Idjakovic

Since 2002, the effects of corrosion on aluminum alloys of nuclear purity in ordinary water of the spent fuel storage pool of the RA re search reactor at VINCA Institute of Nuclear Sciences have been examined in the frame work of the International Atomic Energy Agency Coordinated Research Project "Corrosion of Research Reactor Aluminum Clad Spent Fuel in Water". Coupons were ex posed to the pool water for a period of six months to six years. The second part of this study comprises extensive results obtained by detailed visual and microscopic examinations of the surfaces of the coupons and represents an integral part of the first report on the topic, previously presented in this journal.


Worldview ◽  
1984 ◽  
Vol 27 (3) ◽  
pp. 21-22
Author(s):  
Daniel Poneman

In May, 1974, the Indian Government detonated a "peaceful nuclear explosion." The device contained heavy water supplied by the United States and plutonium that had been reprocessed from the spent fuel of a research reactor supplied by Canada. That event shocked the governments involved in international nuclear commerce into greater efforts to prevent the diversion of civil nuclear assistance to military purposes. By 1976, France and West Germany had joined the United States in pledging not to export facilities for the production of plutonium. Two years later the major suppliers agreed upon guidelines intended to ensure that international safeguards would be applied to all sensitive nuclear exports.


Author(s):  
V. Wittebolle

Abstract In Belgium 57% of the electricity is presently generated by 7 nuclear units of the PWR type located in Doel and Tihange. Their total output amounts to 5632 MWe. Part of the spent fuel unloaded from the first three units has been sent till 2000 for reprocessing in the Cogema facility at La Hague. As the reprocessing of the spent fuel produced by the last four units is not covered by the contracts concluded with Cogema, Synatom, the Belgian utilities’ subsidiary in charge of the front- and back-end of the nuclear fuel cycle for all PWR reactors in Belgium, decided to study the possible solutions for a temporary storage of this spent fuel. End of 1993, the Belgian government decided that reprocessing (closed cycle) and direct disposal (open cycle) of spent fuel had to be considered as equal options in the back-end policy for nuclear fuel in Belgium. The resolution further allowed continued execution of a running reprocessing contract (from 1978) and use of the corresponding Pu for MOX in Belgian NPP’s, but requested a reprocessing contract concluded in 1990 (for reprocessing services after 2000) not to be executed during a five-year period. During this period priority was to be given to studies on the once-through cycle as an option for spent fuel management. Figure 1 is a chart showing the two alternatives for the spent fuel cycle in Belgium. In this context, Synatom entrusted Belgatom1 to develop a dedicated flask (called “bottle”) for direct disposal of spent fuel, to perform a design study of an appropriate encapsulation process and to prepare a preliminary feasibility study of a complete spent fuel conditioning plant. Meanwhile preparation works were made for the construction of an interim storage facility on both NPP sites of Doel and Tihange in order to meet increasing storage capacity needs. For selecting the type of interim storage facility, Belgatom performed a technical-economical analysis. Considerations of design and safety criteria as well as flexibility, reversibility, technical constraints, global economical aspects and construction time led to adopt dry storage with dual purpose casks (in operation since end 1995) for the Doel site and wet storage in a modular pool for the Tihange site (in operation since 1997). In parallel, ONRAF/NIRAS, the Belgian Agency for the management of radioactive waste and enriched fissile materials and the Belgian nuclear research centre, SCK•CEN, conduct underground investigations in view of geological disposal. The paper describes the methodology that Belgatom has developed to provide the utilities with appropriate solutions (reracking, dry storage in casks, wet storage in ponds, etc.) and how Belgatom demonstrated also the feasibility of spent fuel conditioning with a view to direct disposal in clay layers. The spent fuel storage facilities in operation in Belgium and designed and built by Belgatom are then briefly presented.


Author(s):  
A. Boschi ◽  
E. Cimini ◽  
F. Pagni ◽  
L. Parracone ◽  
M. Pocai ◽  
...  

The RTS-1 “Galileo Galilei” is an open pool research reactor light water moderated and cooled. It had a maximum thermal output of 5 MWth and an average thermal flux of 5 E+13 n/cm2sec. It became critical for the first time on April 1963 and it was definitely shutdown in March 1980. The reactor is situated at CISAM (Joint Centre of Studies and Military Application - Italian Ministry of Defence), S. Piero a Grado, Pisa, Italy, and its decommissioning is in progress. In this paper the strategy adopted to achieve the green status of the reactor site is discussed, with particular attention on the different steps to be done according to the national laws. Emphasis is placed on the characteristics of two different conditions required, namely Passive Protective Custody, which is a step necessary to allow the decay of the radioactive materials present into the plant to decrease the radiological risk to operate safely, and Unconditioned Release, in which all the materials can be released without radiological restrictions. Another aspect discussed in this paper is the effort spent on the determination of the radioisotopic abundance of the reactor components, the personal dose evaluation due to the necessary activities to achieve two different status of “Passive Protective Custody” and “Unconditioned Release” and the waste characterisation. The necessary authorisations to start decommissioning has been obtained as far as concern the removal of spent fuel and the dismantling of some experimental equipments.


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