Published February 1970 | Version v1
Miscellaneous Open

Control of fissile materials losses during processing of Rapsodie fuels

Creators

  • 1. Direction du Centre d'Etudes Nucleaires de Saclay, Departement d'Electronique Generale, Service d'Electronique des Reacteurs (France)
  • 2. Direction des Materiaux et des Combustibles Nucleaires, Departement de Chimie, Services de Chimie des Combustibles Irradies, Service de Genie Chimique Radioactf, Section de Traitement des Combustibles au Plutonium (France)

Description

Equipment is described which has been designed to control losses of fissile materials in leached hulls during the processing of fuel from Rapsodie in the pilot plant A.T.1 (La Hague). In this method the leached hulls are placed in basket and irradiated using a neutron generator; the delayed neutrons emitted after irradiation are then counted. It is possible to control a basket containing 10 kilos of leached hulls in 30 minutes, and to detect 50 mgs of uranium 235. (authors)

Abstract (French)

On decrit un equipement qui a ete concu pour controler les pertes de matieres fissiles dans les morceaux de gaines de combustibles irradies, au cours des operations de traitement du combustible de RAPSODIE, dans l'ateller pilote A.T.1 (La Hague). La methode consiste a irradier a l'aide d'un generateur de neutrons les morceaux de gaines contenus dans un panier, et a compter les neutrons retardes emis apres irradiation. Il est possible de controler un panier contenant 10 kilogrammes de gaines en 30 minutes, et detecter une quantite de 50 milligrammes d'uranium 235. (auteurs)

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Additional details

Additional titles

Original title (French)
Controle des pertes de matieres fissiles dans le traitement du combustible de Rapsodie

Publishing Information

Imprint Pagination
28 p.
Report number
CEA-R--3961

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
54027863
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
Descriptors DEI
BORON LINED COUNTERS; CEA LA HAGUE; CEA SACLAY; DELAYED NEUTRON ANALYSIS; LEACHING; NEUTRON FLUX; NEUTRON GENERATORS; PLUTONIUM DIOXIDE; POST-IRRADIATION EXAMINATION; QUANTITATIVE CHEMICAL ANALYSIS; RAPSODIE REACTOR; SENSITIVITY; SPENT FUEL ELEMENTS; TBP; TIME RESOLUTION; URANIUM 235; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BREEDER REACTORS; BUTYL PHOSPHATES; CEA; CHALCOGENIDES; CHEMICAL ANALYSIS; DISSOLUTION; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; ESTERS; EVEN-ODD NUCLEI; FAST REACTORS; FBR TYPE REACTORS; FRENCH ORGANIZATIONS; FUEL ELEMENTS; FUEL REPROCESSING PLANTS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MEASURING INSTRUMENTS; MINUTES LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NEUTRON DETECTORS; NEUTRON SOURCES; NONDESTRUCTIVE ANALYSIS; NUCLEAR FACILITIES; NUCLEAR REACTION ANALYSIS; NUCLEI; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PARTICLE SOURCES; PHOSPHORIC ACID ESTERS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; PLUTONIUM REACTORS; PROPORTIONAL COUNTERS; RADIATION DETECTORS; RADIATION FLUX; RADIATION SOURCES; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESOLUTION; SEPARATION PROCESSES; SODIUM COOLED REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; TEST FACILITIES; TEST REACTORS; TIMING PROPERTIES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
3 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses