scholarly journals FUEL MANAGEMENT AND INVENTORY IN THE EBR-II FUEL CYCLE

1965 ◽  
Author(s):  
I.G. Dillon ◽  
L. Jr. Burris ◽  
M. Levenson
Keyword(s):  
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):  
Yoon Hee Lee ◽  
Jongsoon Song ◽  
Jongkuk Lee ◽  
Kunjai Lee

There are three options for spent fuel management, recycle, once-through and wait and see. The national policy for spent fuel in Korea is “wait and see” and it has to be clearly decided for spent fuel management. The final disposal is the last stage of the fuel cycle and it is essential even though the recycling option will be chosen for spent fuel management policy. And the long-term strategy for spent fuel management considering safety and retrievability is needed. In this study, once-through fuel cycle was focused on for back-end fuel cycle. The international trend for SF management policy and the Korean situation has been investigated. The once-through back-end fuel cycle scenarios has been developed and screened in point of technical and economical aspect. The optimal scenario has been derived by relative comparison and the long-term SF management strategy has been proposed which satisfies both domestic conditions and international trends.


Author(s):  
S. Zheng ◽  
R. Meinl ◽  
J. Stephens

The EPR™ reactor has been designed by AREVA to support economical fuel cycles. The progress in the reactor and systems design improves the reactor safety, and allows the EPRTM reactor to support the large range of high performance fuel management strategies covering cycle length from 12 to 24 months. Different fuel management strategies with 12, 18 and 24 month cycles are described. Economic analyses are performed to illustrate the low uranium consumption and the high fuel cycle performance compared with the fuel managements implemented in most current traditional PWR reactors.


Author(s):  
Kaichao Sun ◽  
Michael Ames ◽  
Thomas Newton ◽  
Lin-wen Hu

A neutronic analysis of the Massachusetts Institute of Technology Research Reactor (MITR) is performed using state-of-the-art computational tools: the continuous-energy Monte Carlo code MCNP5 and the point-depletion code ORIGEN2.2. These codes are externally coupled by the in-house code package, MCODE (MCNP-ORIGEN Coupled Depletion Program), more recently, it being extended to MCODE-FM (Fuel Management). The latter features automated input file generation, data manipulation, and post-processing of the output data for the fuel cycle analysis, so that it is used to simulate the fuel management of the MITR. MCODE-FM also has an optional criticality search algorithm to simulate control blade movement. The code validation is carried out by comparing the calculated results to experimental data. Two sets of the comparisons are made in the present paper: 1) the Xe-135 reactivity effect during the reactor start-up and shutdown and 2) the thermal and fast neutron flux in an irradiation capsule in the reactor core. Good agreements have been found. The validated MCODE-FM is therefore useful for neutronic analysis and the fuel cycle simulation of the MITR. The time dependent variation of the key parameters, viz. the control blades’ axial position (maintaining criticality) and the fissile inventory in the fuel, is presented.


2005 ◽  
Vol 151 (2) ◽  
pp. 177-191 ◽  
Author(s):  
Ehud Greenspan ◽  
Pavel Hejzlar ◽  
Hiroshi Sekimoto ◽  
Georgy Toshinsky ◽  
David Wade

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