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Criticality Studies in a Pilot Plant for Processing MTR-Type Irradiated Fuels; Estudios de Criticidad de una Planta Piloto para el Tratamiento de Combustibles Irradiados Tipo ' MTR '

Conference:

Abstract

A number of theoretical studies on nuclear safety have been carried out in a pilot plant being constructed at the Junta de Energia Nuclear in Madrid for processing irradiated fuels from the MTR-type experimental reactor JEN-1. The study was carried out working with aqueous and organic solutions at two levels of {sup 235}U enrichment - 20% and 93%. The paper is divided into two main parts: the first deals with the individual items of equipment, and the interactions between these are studied in the second part. The calculations in this second part have been made using three different methods to make it more certain that the system as a whole can never be critical. The first method employed is based on the solid angle concept and makes it possible to fix the maximum {sup 235}U concentrations within the system. The second method, based on the albedo, supplies the value of the multiplication factor K of the whole assembly as a function of the concentration of {sup 235}U. In the last part, the distribution of the equipment is compared with other similar systems and experimental tests from other sources. Finally, the paper specifies the conditions for working the installation which ensure  More>>
Authors:
Pereira Sanchez, G.; Uriarte Hueda, A. [1] 
  1. Junta de Energia Nuclear, Division de Materiales Madrid (Spain)
Publication Date:
May 15, 1966
Product Type:
Conference
Report Number:
IAEA-SM-70/26
Resource Relation:
Conference: Symposium on Criticality Control of Fissile Materials, Stockholm (Sweden), 1-5 Nov 1965; Other Information: 14 refs., 10 tabs., 6 figs.; Related Information: In: Criticality Control Fissile of Materials. Proceedings of the Symposium on Criticality Control of Fissile Materials| 772 p.
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; ALBEDO; CONCENTRATION RATIO; CRITICALITY; INTERACTIONS; JEN-1 REACTOR; MODERATELY ENRICHED URANIUM; MULTIPLICATION FACTORS; PILOT PLANTS; RADIATION ACCIDENTS; RADIATION PROTECTION; SOLUTIONS; SPENT FUELS; URANIUM 235
OSTI ID:
22117269
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
Spanish
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M2179073890
Submitting Site:
INIS
Size:
page(s) 679-697
Announcement Date:
Aug 01, 2013

Conference:

Citation Formats

Pereira Sanchez, G., and Uriarte Hueda, A. Criticality Studies in a Pilot Plant for Processing MTR-Type Irradiated Fuels; Estudios de Criticidad de una Planta Piloto para el Tratamiento de Combustibles Irradiados Tipo ' MTR '. IAEA: N. p., 1966. Web.
Pereira Sanchez, G., & Uriarte Hueda, A. Criticality Studies in a Pilot Plant for Processing MTR-Type Irradiated Fuels; Estudios de Criticidad de una Planta Piloto para el Tratamiento de Combustibles Irradiados Tipo ' MTR '. IAEA.
Pereira Sanchez, G., and Uriarte Hueda, A. 1966. "Criticality Studies in a Pilot Plant for Processing MTR-Type Irradiated Fuels; Estudios de Criticidad de una Planta Piloto para el Tratamiento de Combustibles Irradiados Tipo ' MTR '." IAEA.
@misc{etde_22117269,
title = {Criticality Studies in a Pilot Plant for Processing MTR-Type Irradiated Fuels; Estudios de Criticidad de una Planta Piloto para el Tratamiento de Combustibles Irradiados Tipo ' MTR '}
author = {Pereira Sanchez, G., and Uriarte Hueda, A.}
abstractNote = {A number of theoretical studies on nuclear safety have been carried out in a pilot plant being constructed at the Junta de Energia Nuclear in Madrid for processing irradiated fuels from the MTR-type experimental reactor JEN-1. The study was carried out working with aqueous and organic solutions at two levels of {sup 235}U enrichment - 20% and 93%. The paper is divided into two main parts: the first deals with the individual items of equipment, and the interactions between these are studied in the second part. The calculations in this second part have been made using three different methods to make it more certain that the system as a whole can never be critical. The first method employed is based on the solid angle concept and makes it possible to fix the maximum {sup 235}U concentrations within the system. The second method, based on the albedo, supplies the value of the multiplication factor K of the whole assembly as a function of the concentration of {sup 235}U. In the last part, the distribution of the equipment is compared with other similar systems and experimental tests from other sources. Finally, the paper specifies the conditions for working the installation which ensure that a nuclear accident can never occur. (author) [Spanish] Se ha efectuado una serie de estudios teoricos sobre la seguridad nuclear de una planta piloto, que se encuentra en construccion en la Junta de Energfa Nuclear situada en Madrid, para el tratamiento de combustibles irradiados procedentes del reactor experimental JEN-1 del tipo MTR. El estudio se ha realizado utilizando disoluciones, tanto acuosas como organicas, con dos grados de enriquecimiento, 20% y 93% en {sup 235}U. Este trabajo comprende dos partes principales: en la primera se han considerado las distintas unidades del equipo individualmente y en la segunda se han estudiado las interacciones entre ellas. El calculo de esta segunda parte se ha hecho por tres metodos diferentes para tener una mayor seguridad de que el sistema total nunca puede ser critico. El primer metodo utilizado esta basado en el concepto de angulo solido y ha permitido fijar las maximas concentraciones de {sup 235}U dentro del sistema. El segundo, basado en el 'Albedo' ha suministrado el valor del factor de multiplicacion, K, de todo el conjunto en funcion de la concentracion de {sup 235}U, En la ultima parte se compara la distribucion del equipo con otros sistemas semejantes y ensayos experimentales de otras fuentes. Finalmente se fijan las condiciones de trabajo de la instalacion para que nunca pueda ocurrir un accidente de tipo nuclear. (author)}
place = {IAEA}
year = {1966}
month = {May}
}