Annual progress report 1996 on exploring innovative approaches, reactor safety, radioactive waste management and disposal and decommissioning research areas of the "Nuclear fission safety" programme 1994-98

Directorate-General For Research And Innovation European Commission

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Nuclear energy and safety

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• Publié par: DIRECTORATE-GENERAL-FOR-RESEARCH-AND-INNOVATION-EUROPEAN-COMMISSION
• Nombre de lectures: 17
• Langue: English
• Poids de l'ouvrage: 14 Mo

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ISSN 1018-5593
European Commission
nuclear science
and technology
Annual progress report 1996 on exploring
innovative approaches, reactor safety,
radioactive waste management and disposal
and decommissioning research areas of the
'Nuclear fission safety' programme 1994-98
Report
EUR 17852 EN European Commission
ι ι -1* ■ - ? ,.
Annual progress report 1996 on exploring
innovative approaches, reactor safety,
radioactive waste management and disposal
and decommissioning research areas of the
'Nuclear fission safety' programme 1994-98
Directorate-General
Science, Research and Development
1997 EUR 17852 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
A great deal of additional information on the European Union is available on the Internet.
It can be accessed through the Europa server (http://europa.eu.int)
Cataloguing data can be found at the end of this publication
Luxembourg: Office for Official Publications of the European Communities, 1997
ISBN 92-828-1097-6
© European Communities, 1997
Reproduction is authorized provided the source is acknowledged
Printed in Luxembourg FOREWORD
The Council of the European Union adopted with its decision 94/920/Euratom of 15 December
1994 (O.J. N° L 361 dated 31 Dec. 1994, pp. 143­145) the specific programme "Nuclear
Fission Safety 1994­1998" under a framework programme of Community activities in the field
of research and training for the European Atomic Energy Community (Euratom) 1994­19981.
The specific programme "Nuclear Fission Safety" which has a total budget of 170.5 million
ECU consists of five research areas: Α­Exploring Innovative Approaches; B­Reactor Safety;
C­Radioactive Waste Management and Disposal and Decommissioning; D­Radiological Impact
on Man and the Environment; E­Masterinç Events of the Past.
Ό
This report covers the progress of the 62 multi-partner research projects running in 1996, for
the area Α, Β and C of the programme, under the responsibility of European Commission Unit
XII/F/5 "Nuclear Fuel Cycle, Radioactive Waste".
The running contracts are those resulting from the selection procedure of the proposals
received at the first deadline of the call for proposals on shared cost projects and concerted
actions.
Cooperation among teams within the Member States is assured through the presence of at least
two partners from different countries.
The programme also includes awards of training and mobility grants, as well as international
cooperation agreements and concerted actions with states outside of the European Union.
The European Commission is assisted in the implementation and the management of the
programme by the Consultative Committee for the Programme (see the annexed list
Committee members).
A total of 20 "clusters" have been set up for the areas Α, Β and C to assure the best follow up
of groups of projects covering special items of the programme.
An introduction to each area of research gives a general overview of the objectives and items
being developed. The objectives, the working programme and a synopsis of progress and
results achieved for each contract in 1996 are presented as prepared by the contractors, under
the responsibility of the project coordinator.
The European Commission wishes to express its gratitude to all scientists who have
contributed to this report.
R. Simon
Programme Manager for the Areas Α, Β and C
' Council decision 94/268/Euratom of 26 April 1994 - O.J. N° L 115 of 6 May 1994, pp. 31-37. This Euratom
framework programme is linked to activity one of the Fourth Framework Programme of the EC. RTD activities
1994-1998 (Co-decision N° 1100/94/EC of the European Parliament and of the Council of 26 April 1994-OJ. N° L 126
of 18 May 1994). MEMBERS OF THE CONSULTATIVE COMMITTEE1
FOR THE SPECIFIC PROGRAMME TS THE FIELD OF
"NUCLEAR FISSION SAFETY" 1994­1998
AUSTRIA W. REITER
D. WESELKA
BELGIUM D. CAMMAERTS
J­M. MORELLE
TH. VANRENTERGEM
DENMARK J. HOVGAARD
Β. MAJBORN
Κ. ULBAK
FINLAND T. HAAPALEHTO
L. MATTILA
FRANCE C. COURTOIS
A. FLÜRY­HERARD
M. LIVOLANT (Chairman)
GERMANY S. KÖSTER
H­Η. LANDFERMANN
H. SAMEITH
GREECE L. SIDERIS
IRELAND J. D. CUNNINGHAM
N. HUGHES
ITALY G. SAPONARO
R. TAVONI
LUXEMBOURG C. BACK
C. HASTERT
NETHERLANDS P. J. DE MUNK
R.W.P. STEUR
J.P.F. TUSSEN
PORTUGAL A. O. BETTENCOURT
J. PEDROSO DE LIMA
SPAIN J. ARANA LANDA
J.M. MARTÍNEZ­VAL PEÑALOSA
SWEDEN L. ANDERMO
U. BÄVERSTAM
UNITED KINGDOM R. JACKSON
P. STOREY
H. WALKER
COMMISSION E. ANDRETA
T. McMENAMIN (Secretary)
'This Committee was established by the Council Decision 94/920/Euratom of 15 December 1994, Ait. 5, Par. 2
(OJ. N°L361pp. 143­145)
IV Table of Contents
FOREWORD m
THE CONSULTATIVE COMMITTEE FOR THE SPECIFIC PROGRAMME
IN THE FIELD OF "NUCLEAR FISSION SAFETY" IV
PROGRESS OF THE R&D WORK 1
A. Exploring Innovative Approaches
Introduction 5
A.l Conceptual Reactor Safety Features
A. 1.1-1 Thermalhydraulics of large pools with immersed heat
exchangers and natural convection heat transfer - POOLTHY
(FI4I-CT95-0003) 7
A. 1.1-2 Assessment of passive safety injection systems of advanced
light water reactors - APSI (F14I-CT95-0004) 15
A. 1.1-3 European BWR-R&D-cluster for innovative passive safety
systems - IPSS (FI4I-CT95-0005) 22
A. 1.1-4 Technology enhancement for passive safety systems - TEPSS
(FI4I-CT95-0008) 30
A. 1.1-5 System for emergency core cooling through high performance
steam injector -SYNTHESIS (FT4I-CT95-0001) 36
A.2 Fuel Cycle Concepts (Partitioning and transmutation)
A.2.1-1 Supporting nuclear data for advanced MOX fuels
(FI4I-CT95-0002)9
A.2.1-2 Evaluation of possible P&T strategies and of associated means
to perform them. (FI4I-CT95-0006) 45
A.2.1-3 Thorium cycles as a nuclear waste management option
(FI4I-CT96-0011) 51
A.2.1-4 Impact of the accelerator-based technologies on nuclear fission
safety - IABAT (FI4I-CT96-00T2) 54
A.2.2-1 New partitioning techniques - NEW PART
(FI4I-CT96-0010) 67
A.2.3-1 Joint EFTTRA experiment on Am transmutation
(FI4I-CT95-0007) 73
A.2.3-2 Neutron driven nuclear transmutation by adiabatic resonance
crossing - TARC (FI4I-CT96-0009) 76
V Β. Reactor Safety
Introduction 81
B.l In-vessel Core Degradation and Coolability
B. 1.1-1 Experimental and computational modelling of corium
formation and behaviour during a severe accident in a light
water reactor -Investigation of core degradation - COBE
(FI4S-CT95-0013) 83
B. 1.3-1 Core melt-pressure vessel interactions during a light water
reactor severe accident - MVI (FI4S-CT95-0007) 91
Β. 1.4-1 Behaviour of the reactor pressure vessel under mechanical and
thermal loadings caused by core melt-down and steam
explosion accidents - RPV under severe accident loadings
(FI4S-CT95-0002) 98
B.2 Ex-vessel Corium Behaviour and Coolability
B.2.1-1 Thermochemical modelling and data - THMO
(FI4S-CT95-0008) 103
B.2.2-1 Investigations on the phenomenology of ex-vessel core-melt
behaviour - COMAS (FI4S-CT95-0003) 107
B.3 Source term
B.3.1-1 Fission product release and speciation - RSP
(FI4S-CT95-0006) 112
B.3.1-2 Revaporisation of tests on samples from PHEBUS fission
products - RVP (FI4S-CT96-0019)8
B.3.2-1 Iodine chemistry - IC (FI4S-CT95-0005) 121
B.3.2-2 Aerosol physics in containment - APC (FI4S-CT95-0016) 127
B.4 Containment Performance and Energetic Containment Threats
B.4.1-1 Multidimensional simulation of hydrogen distribution and
turbulent combustion in severe accidents - H2n and
combustion - HDC (FI4S-CT95-0001) 134
B.4.1-2 Improved modelling of turbulent hydrogen combustion and
catalytical recombination for hydrogen mitigation - HYMI
(FI4S-CT96-0017) 138
B.4.2-1 INCON - Innovative containment cooling for double concrete
containment (FI4S-CT95-0011) 144
B.4.4-1 Benchmark on containment penetration sealing areas behaviour
- ATHERMIP (FI4S-CT95-0010) 151
VI B.5 Supporting Activities
B.5-1 Benchmark exercise on expert judgement techniques in PSA
level 2 - BE-JET (FI4S-CT95-0012) 154
B.5.1-1 Development of methodology for the evaluation of severe
accident managment strategies - SAMEM
(FI4S-CT95-0015) 162
B.5.2-1 Dosimetry and irradiation programmes of Ames European
network - AMES (FI4S-CT95-0004)8
B.5.2-2 Relation between different measures of exposure-induced shifts
in ductile-brittle transition temperatures - REFEREE
(FI4S-CT95-0009) 174
B.5.2-3 Evaluation of techniques for assessing corrosion cracking in
dissimilar metal welds - DISWEC (FI4S-CT95-0018) 178 '
C. Radioactive Waste Management and Disposal and Decommissioning
Introduction 187
C.l Safety Aspects of Waste Disposal
C. 1.1-1 SPA: Spent fu