Quality control for low and medium active wasteTask 3

Directorate-General For Translation European Commission

Description

Characterization of radioactive waste forms: A series of final reports (1985-89): No 42
Nuclear energy and safety

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• Publié par: EUROPEAN-COMMISSION
• Nombre de lectures: 14
• Langue: English
• Poids de l'ouvrage: 3 Mo

Extrait

ISSN 1018-5592
Commission of the European Communities
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Quality control for low and medium
active waste
Task 3
Characterization of radioactive waste forms
A series of final reports (1985-89) - No 42
SÍ5
Report
EUR 13878 EN Commission of the European Communities
nuclear science
and technology
Quality control for low and medium
active waste
Task 3
Characterization of radioactive waste forms
A series of final reports (1985-89) - No 42
A. Saas
CEN Cadarache
DRDD/SCECA
Bât. 352
BPN°1
F-13108 St Paul-les-Durance
Final report
This report was prepared for the European Atomic Energy Community's
cost-sharing research programme on radioactive waste management
and disposal (Task 3 - Section 5) under contract No FI1W/0220
Directorate-General
Science, Research and Development
PARL EUROP. Biblioth.
1991 N-C EUR 13878 ÍN
CI. Published by the
COMMISSION OF THE EUROPEAN COMMUNITIES
Directorate-General
Telecommunications, Information Industries and Innovation
L-2920 Luxembourg
LEGAL NOTICE
Neither the Commission of the European Communities nor any person
acting on behalf of the Commission is responsible for the use which might
be made of the following information
Cataloguing data can be found at the end of this publication
Luxembourg: Office for Official Publications of the European Communities, 1991
ISBN 92-826-3263-6 Catalogue number: CD-NA-13878-EN-C
© ECSC-EEC-EAEC, Brussels · Luxembourg, 1991
Printed in Luxembourg CONTENTS
Pages
ABSTRACT
IX - Langue française
- English language XI
1 - PREAMBULE 1
2 - INTRODUCTION 3
3 - TASK I - OPTIMISATION AND VALIDATION OF SAMPLING
5
PROCEDURES
5 3.1- Introduction
3.2 - Representative sampling from full-scale
6
packages
3.2.1 - Theoretical calculations 7
3.2.2 - Practical applications 17
3.2.3 - Conclusion 22
23 3.3 - Evaluation of homogeneity
23 3.3.1 - Method of analysis
3.3.2 - Applications6
3.3.3 - Discussion 30
3.3.4 - Conclusion2
3.4 - References3 Pages
4 - TASK II - MEASUREMENT OF ALPHA AND BETA-EMITTING
RADIONUCLIDES IN FULL-SIZE EMBEDDED
35 NUCLEAR WASTES
4.1 - Introduction 35
4.2 - Determination of Sr-90 in nuclear waste
3
solutions
4.2.1 - Procedure6
4.2.2 - Experimental results and discussion 37
4.2.3 - Analysis of one real liquid waste 43
4.2.4 - Conclusion 4
4.3 - Determination of Plutonium 241 in nuclear
4
wastes
4.3.1 - Procedure9
4.3.2 - Applications 54
4.3.3 - Conclusion
4.4 - Measurement of Tritium and Carbon 14 in ionic
exchangers resins embedded in polymers 60
4.4.1 - Procedure by combustion in tubular oven 61
4.4.2 -e by acid digestion2
4.4.3 - Procedure byn with oxygen in
64
a closed vessel
4.4.4 - Conclusion 67
4.5- References8
-IV Pages
5 - TASK III - NON-DESTRUCTIVE ANALYTICAL PROCEDURE FOR
ALPHA AND LONG LIFE BETA NUCLIDES
IN EMBEDDED WASTES 69
5.1 - Scope of the research
5.2 - Work programme 70
5.2.1 - Alpha measurements
5.2.2 - Betas
5.3 - Alpha measurements1
5.3.1 - Measurements of real waste packages
and samples ''
5.3.2 - Detection limits 73
5.3.3 - Validation
5.4 - Beta measurements6
5.4.1 - Principle
5.4.2 - Means employed
5.4.3 - Preliminary experiments 77
5.4.4 - Feasabilitys9
5.4.5 - Conclusion 80
5.5 - References2
6 - TASK IV - DETECTION AND MEASUREMENT OF GAS GENERATION
FROM RADIOLYSIS BY WASTE/MATRIX INTERACTION
(BITUMEN)3
6.1 - Scope of the research
6.2 - Work programme 8
6.2.1 - Gas tightness experiments 85
6.2.2 - Sweeping gass
6.2.3 - Representativity of samples
6.2.4 - Testing on industrial waste
6.3 - Gas tightness experiments6
6.4 - Sweeping gass7
6.5 - Representativity of samples 8
6.6 - Testing on industrial waste 90 Pages
6.7 - Conclusion 92
93 6.8 - Appendix
7 - TASK V - DETECTION AND MEASUREMENT OF EXTERNAL
GAMMA IRRADIATION INDUCED GASES
EVOLVED BY BITUMINISATES - EVALUATION OF
THE PART OF RELEASED AND TRAPPED GASES IN
95 ORDER TO PREDICT FULL-SIZE DRUMS SWELLING
95 7.1- Introduction
96 7.2 - Description of samples
7.2.1 - Waste content of bituminisates 95
7.2.2 - Elementary analysis of waste form6
7.3 - Experimental conditions 98
7.4 - Evolving of radiolysis gases
7.5 - Gamma induced swelling 101
7.6 - Production rate - Radiochemical yields 102
7.7 - Diffusion experiments4
7.8 - Extraction of trapped gases
107.8.1 - Experimental conditions
108 7.8.2 - Results
120 7.9 - Conclusion
8 - TASK VI - MEASUREMENT ON FREE LIQUID IN FULL-SCALE
121
DRUM
121 8.1- Scope of the research
122 8.2 - Work programme
8.2.1 - Tests on cemented wastes 122
8.2.2 - Control procedure
8.3 - Experimments with "SOLO 40" meter3
8.3.1 - Description 12
8.3.2 - Control procedure
8.3.3 - Tests on reference drums 12
8.3.4 -s on real cemented waste7
8.3.5 - Calibrations
VI Pages
8.4 - Experiments with "TROXLER" meter 129
8.4.1 - Description 12
8.4.2 - Control procedure
8.4.3 - Tests on reference drums
8.4.4 -s on real cemented waste 131
8.5 - Conclusion 134
-VII