Hostname: page-component-586b7cd67f-rdxmf Total loading time: 0 Render date: 2024-11-24T13:33:47.991Z Has data issue: false hasContentIssue false

Vitrocerus: An alternative for processing MTR spent fuel from research reactors

Published online by Cambridge University Press:  23 March 2012

P.A Arboleda
Affiliation:
Consejo Nacional de Investigaciones Científicas y Técnicas (CONICET). Avda. Rivadavia 1917, CP 1033 AAJ, Buenos Aires, Argentina Instituto Balseiro. U de Cuyo. Av E Bustillo 9500, S.C de Bariloche. Argentina
D.S Rodríguez
Affiliation:
Comisión Nacional de Energía Atómica (CNEA). Centro Atómico Bariloche (CAB) - Av.E.Bustillo 9500 - (8400) - S. C. de Bariloche - (RN). Argentina Instituto Balseiro. U de Cuyo. Av E Bustillo 9500, S.C de Bariloche. Argentina
M.O Prado
Affiliation:
Consejo Nacional de Investigaciones Científicas y Técnicas (CONICET). Avda. Rivadavia 1917, CP 1033 AAJ, Buenos Aires, Argentina Comisión Nacional de Energía Atómica (CNEA). Centro Atómico Bariloche (CAB) - Av.E.Bustillo 9500 - (8400) - S. C. de Bariloche - (RN). Argentina Instituto Balseiro. U de Cuyo. Av E Bustillo 9500, S.C de Bariloche. Argentina
Get access

Abstract

Research reactors spent fuels disposal is a problematic area that conduces to the quest of feasible solutions for ensure safe destination of the spent fuels. In this work, a new method for processing spent fuel from MTR reactors is presenting. The main objective of this process, is the immobilization of principal radioactive elements that are present in the spent fuel, in order to achieve a suitable material which could be temporally stored safely. The Vitrocerus method involves ordinary physical procedures performed in a hot cell. It differs from conventional vitrification because there is a reduction in volume of glass material added.

The process propose the ceramization of a mixture of spent fuel plates (wich were milled and calcined previously) with natural uranium oxide (U3O8) to obtain the desired isotopic dilution (to low the U235 enrichment). At the same time, a small fraction of VG98/12 glass [1] was added to enhance low temperature sintering. The treatment and conditioning tasks proposed in Vitrocerus were tested on MTR fuel miniplates that simulate a real U3Si2 dispersed in Al fuel, which were successfully transformed into ceramic sintered pellets [2,3] with low enrichment, structural integrity, outstanding mechanical properties and water corrosion resistance. Eventually these pellets could be stored safely in an interim dry storage facility.

Type
Articles
Copyright
Copyright © Materials Research Society 2012

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Kahl, L., et al. . “Preparation and Characterization of an Improved Borosilicate Glass for the Solidification of High Level Radioactive Fission Product Solutions (HLW)”. KfK 3251, april 1982 Google Scholar
2. Russo, D.O., Rodríguez, D.S., et al. . “Acondicionamiento de combustibles gastados de reactores nucleares de investigación en matrices cerámicas”. Presented in CONAMET-SAM / SIMPOSIO MATERIA 2002. November 2002, Santiago de Chile, Chile.Google Scholar
3. Arboleda, P.A., Rodríguez, D.S., Prado, M.O.Acondicionamiento de Elementos Combustibles Irradiados de Reactores de Investigación”. Master degree thesis. Universidad de Cuyo. Instituto Balseiro. May 2011 Google Scholar
4. Bevilaqua, A.M, Audero, M.A. “Inmovilización de residuos líquidos de alta actividad simulados en vidrios sinterizados”. PhD thesis. Instituto Balseiro. CNEA. Argentina 1992.Google Scholar
5. Nuclear waste materials handbook. “ Waste form test methods DOE/TIC 11400”. Material Characterization Center, 1981 Google Scholar
6. NLT 346/90. “ Resistencia a Compresión Diametral (ensayo Brasileño) de Mezclas bituminosas Google Scholar
7. Garrote, E.. “Nuevo procedimiento de ensayo para evaluar la tenacidad de las mezclas bituminosas”; (2007) (Tesina)Google Scholar
8. Nassini, H.E.P, Troyano, C.N.F, Bevilaqua, A.M, Bergallo, J.E. “Diseño conceptual de un sistema para el almacenamiento interino en seco del combustible gastado de la Central Nuclear Atucha”. Revista de la CNEA. Año 5-No 19–20. Diciembre 2005. Argentina.Google Scholar
9. Dlouhy, and Boccaccini, A.R.. “ Borosilicate and lead silicate glass matrix composites containing pyrochlore phases for nuclear waste encapsulation Comp. Sci. Tech. 56 (1996), p. 1415 10.1016/S0266-3538(96)00102-9Google Scholar