The HAW project

European Commission Directorate-General For Research And Innovation

Description

Test disposal of highly radioactive radiation sources in the Asse salt mine: Documentation and appraisal of the disposal system
Nuclear energy and safety

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• Publié par: EUROPEAN-COMMISSION-DIRECTORATE-GENERAL-FOR-RESEARCH-AND-INNOVATION
• Nombre de lectures: 3
• Langue: English
• Poids de l'ouvrage: 8 Mo

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ISSN 1018-5593
European Commission
nuclear science
and technology
The HAW project: Test disposal of highly
radioactive radiation sources in the Asse salt mine
Documentation and appraisal of the disposal system
Report
EUR 16554 EN European Commission
nuclear science
and technology
The HAW project: Test disposal of highly
radioactive radiation sources in the Asse salt mine
Documentation and appraisal of the disposal system
K. Müller, T. Rothfuchs
GSF, Forschungszentrum für Umwelt und
Gesundheit, GmbH
Theodor-Heuss-Straße 4
D-38122 Braunschweig
Contract No FI2W - CT90-0002
Topical report
This work has been carried out under a cost-sharing contract with the European
Atomic Energy Community in the framework of its fourth R&D programme entitled
'Management and storage of radioactive waste,
Part B, 'Underground laboratories'
Directorate-General
Science, Research and Development
1995 EUR 16554 EN LEGAL NOTICE
Neither the European Commission 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, 1995
ISBN 92-827-4634-8
© ECSC-EC-EAEC, Brussels · Luxembourg, 1995
Reproduction is authorized, except for commercial purposes, provided the source is acknowledged
Printed in Luxembourg ABSTRACT
The primary objective of the HAW-project was to investigate the interaction of high-level radioactive
waste canisters with the final repository medium, rock salt. A further major objective of the research
project was the prototype development and trial of a technical system for the disposal of highly
radioactive canisters in deep disposal boreholes.
The disposal system encompasses all components which are necessary for safe handling of canisters.
Moreover, technical-organizational measures were developed for the execution of the emplacement
and retrieval.
In the present report the components of the final disposal system are described; their position and
function within the overall handling sequence are explained. Special emphasis is placed on questions
of radiation protection and accident prevention, on functional and operational safety, on quality
assurance and examination of documents, materials, preparation, and function, and on documentation.
As far as planning of the disposal technique for a final repository mine is concerned, the experience
gained from the development and operation is recorded in this report, and recommendations are made
for further developments. Problems which occurred during work on the HAW-project were due
partially to test-specific causes and will not occur in this manner, or at all, in a final repository mine.
Ill Foreword
During the reprocessing of spent LWR fuel elements, fission products and actinides to
be treated as radioactive wastes are fused in borosilicate glass and consolidated in
stainless steel canisters. The primary objective of the HAW­project was to investigate
the interaction of such high­level radioactive waste canisters with the final repository
medium, rock salt. A further major objective of the research project was the prototype
development and trial of a technical system for the disposal of highly radioactive
canisters in deep disposal boreholes.
For the simulation of real high­level radioactive waste, special highly radioactive
radiation sources were prepared for the tests in the Asse salt mine by the Battelle­
Pacific Northwest Laboratories in the United States within the scope of a German­
American cooperative contract. The radiation sources were doped with high contents
of the radioisotopes, caesium 137 and strontium 90, in order to obtain representative
test conditions with respect to thermal power and gamma dose rates.
In a final repository the canisters or waste casks must only be deposited. During the
HAW­project, in contrast, the retrieval of the radiation sources upon completion of
the test, or in case of events which render premature retrieval necessary, had to be
taken into account.
The disposal system encompasses all components which are necessary for safe
handling of canisters. Moreover, technical­organizational measures were developed
for the execution of the emplacement and retrieval.
In the present report the components of the final disposal system are described; their
position and function within the overall handling sequence are explained. Special
emphasis is placed on questions of radiation protection and accident prevention, on
functional and operational safety, on quality assurance and examination of documents,
materials, preparation, and function, and on documentation.
As far as planning of the disposal techniques for a final repository mine is concerned,
the experience gained from the development and operation is recorded in this report,
and recommendations are made for further developments. Problems which occurred
during work on the HAW­project were due partially to test­specific causes and will
not occur in this manner, or at all, in a final repository mine. In this report they are
considered only to the extent that they appear significant for future planning.
The beginning of the test disposal had originally been planned for 1987, and its
realization would ultimately have been possible in 1993 after appropriate preparation,
after approval of the disposal system by the mining authorities and TÜV Hannover in
May 1991. In December 1992, however, the German Federal Government decided to
discontinue the project and to discontinue all preparatory operations because of the
uncertain licensing situation.
Despite the premature termination of the test, useful results have been obtained. With
the disposal system, which was available as of December 1989, quarter­annual test
and training runs were performed with simulated sources. Weaknesses were thereby
recognized and eliminated. This is likewise described in detail in the report.
ν Table of Contents
Foreword
1 Introduction 1
2 Objectives, and Boundary Conditions to be Observed 3
3 Conception, Development, Construction, and Approval of
the Components 9
3.1 Single Transport Cask, Type Asse TBI 10
3.2 Grapple 22
3.3 Shielding Bell 3
3.4 Heavy-Duty Trailer
3.5 Fork Lift Above Ground4
3.6 Shaft Transports5
3.7 Multiple Transport Cask, Castor GSF-5
3.8et Cask, GNS-12, and
Transfer Facility in Karlsruhe 40
3.9 Transfery (Transfer Station and Crane System) 41
3.9.1r Station
3.9.2 Crane System 52
3.9.3 Control of the Transfer Facility 6
3.9.4 Transfer of Canister Above Ground for Disposal
and Retrieval
3.10 Mobile Crane, Crosshead 75
3.11 Locomotive, Draw Bar
3.12 Borehole Slider (with Supplementary Shielding) 77
3.13 Disposal Machine 8
3.14 Gallery Transport Vehicle 101
3.15 Use of Fork Lifts Underground
3.16 Load Hooking Devices8
4 Experience During Cold Testing9
4.1 Disposal and Retrieval
4.2 Radiological Check 116
5 Conclusions and Recommendations
6 References 123
VII