Published 1985 | Version v1
Book

Identification at the source of the primary circuit pollution fuel assembly: sipping system

  • 1. Fragema, 92 - Courbevoie (France)

Description

During operation of a PWR nuclear power plant, the radioactivity of the primary coolant is monitored. An increase of the levels of specific radio isotopes such as I 131, Xe 133, Kr 85, may indicate the appearance of a leaking fuel assembly. According to the importance of the level reached during the reactor cycle, it may or not be decided to discard the source of the primary coolant pollution. The decision is based on the criteria from the country regulatory body itself based on both experimental evidence and also efficiency and dimensioning of the waste station operation. At this point, it is necessary to have an instrument for identification of the leaking fuel assembly and even better to have an instrument to measure or characterize the importance of this leaking feature. Two sipping systems will be utilized successively: the online sipping system in the reactor building, and the sipping system located in the fuel building

Abstract (French)

Pendant l'exploitation des centrales nucleaires a eau pressurisee, la radioactivite du circuit primaire est controlee en permanence. Un accroissement de la concentration de radioisotopes I 131, Ke 133, Kr 85 peut signaler l'apparition d'un assemblage combustible non-etanche. Selon l'importance du niveau atteint pendant le cycle en cours, il peut etre decide d'eliminer ou non la source de cette pollution du circuit primaire lors du prochain arret du reacteur. La decision est basee sur les criteres reglementaires du pays, etablis a partir de bases statistiques experimentales et aussi en fonction de l'efficacite et du dimensionnement de la station de traitement des effluents de la centrale. Apres leur dechargement, lorsque ces assemblages combustibles deviennent accessibles, il est necessaire de disposer d'un appareillage pour identifier et meme caracteriser la non-etancheite en effectuant leur ressuage. Deux modes d'examen par ressuage des assemblages pourront etre utilises: le ressuage en ligne effectue pendant le dechargement du combustible, et le ressuage effectue a l'aide des dispositifs de ressuage situes dans le batiment combustible
Part of:
Radioactive waste management, decommissioning, spent fuel storage. V. 1. Waste management principles, decommissioning, dismantling, operations in hot environment

Additional details

Additional titles

Original title (French)
Identification a la source de la pollution radioactive du circuit primaire: dispositifs de ressuage du combustible

Publishing Information

Publisher
Commissariat a l'Energie Atomique.
Imprint Place
Saclay (France)
Imprint Title
Radioactive waste management, decommissioning, spent fuel storage. V. 1. Waste management principles, decommissioning, dismantling, operations in hot environment
Imprint Pagination
358 p.
Journal Page Range
p. 124-135.

Optional Information

Notes
Imprint:Gestion des dechets radioactifs, declassement et demantelement, entreposage des combustibles irradies. V. 1. Principes de gestion des dechets, declassement, demantelement, interventions en milieu ionisant.