Qualitative and quantitative measurement of radionuclides contained in drums of solid wastes
Creators
- 1. Compagnie Generale des Matieres Nucleaires (COGEMA), Centre de la Hague, 50 - Cherbourg (France)
Description
The aim of this work is to extend gamma spectrometry methods to the identification and measurement of the main radionuclides contained in drums of solid wastes. Part one deals with the general problem of variable-distance detection: - experimental evaluation of the yield curve variation for ''source-detector'' distances between 1 centimetre and 5 metres, with a trapezoidal germanium lithium junction. - Evaluation of detection limits for certain ''activation'' and ''fission products'', given the practical variation limits of the measurement parameters (distance, time). Part two gives an estimate of the geometry and position effects of point sources in a 100-litre metal drum containing absorbants of variable density (0.61 to 1.26) for distances ranging from 3 to 5 metres. Two sets of measurements were studied: - fixed positions of various ''sources'' in an immobile drum, - fixed positions of various ''sources'' in a rotating drum. By these analyses a radioactive drum measurement in non-directed geometry is possible
Abstract (French)
Le but de cette etude est d'etendre les methodes de spectrometrie gamma a l'identification et a la mesure des principaux radionucleides contenus dans les futs de dechets solides. La premiere partie permet une analyse d'approche du probleme de detection a distances variables. Evaluation experimentale de la variation des courbes de rendement pour des distances ''source detecteur'' comprises entre 1 centimetre et 5 metres, avec une jonction germanium lithium trapezoidale. Evaluation des limites de detection pour certains ''produits d'activation'' et de ''fission'', compte tenu des limites pratiques d'evolution des parametres de mesure (distance, temps). La deuxieme partie permet d'apprecier les effets de geometrie et de position, des sources ponctuelles dans un fut metallique de 100 litres contenant des absorbants de densite variable (0,61 a 1,26) pour des distances comprises entre 3 et 5 metres. Deux series de mesures ont ete etudiees: - positions fixes de diverses ''sources'' dans un fut immobile, - positions fixes de diverses ''sources'' dans un fut en rotation. L'ensemble de ces analyses permet, en geometrie non canalisee, la faisabilite d'une mesure de fut radioactifAdditional details
Additional titles
- Original title (French)
- Recherche qualitative et quantitative des radionucleides contenus dans les futs de dechets radioactifs, par spectrometrie gamma
Publishing Information
- Journal Title
- Rayonnem. Ionis. Tech. Mes. Prot.
- Journal Issue
- no.3
- Series
- Rayonnem. Ionis. Tech. Mes. Prot.
- ISSN
- 0397-9210
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 13674184
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CALIBRATION; CHEMICAL ANALYSIS; CONTAINERS; EFFICIENCY; EXPERIMENTAL DATA; FISSION PRODUCTS; GAMMA SPECTROSCOPY; LI-DRIFTED GE DETECTORS; POINT SOURCES; RADIOACTIVE WASTES; SOLID WASTES
- Descriptors DEC
- DATA; GE SEMICONDUCTOR DETECTORS; INFORMATION; ISOTOPES; LI-DRIFTED DETECTORS; MEASURING INSTRUMENTS; NUMERICAL DATA; RADIATION DETECTORS; RADIATION SOURCES; RADIOACTIVE MATERIALS; SEMICONDUCTOR DETECTORS; SPECTROSCOPY; WASTES
Optional Information
- Notes
- Tables concerning this article are published in no.4 of the review p. 174-184.