Reactor Safety. PROGRAMME PROGRESS REPORT July-December 1978

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• Langue: English
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COMMISSION
OFTHE EUROPEAN
COMMUNITIES
JOINT RESEARCH CENTRE
Ispra Establishment
Italy
CONFIDENTIAL
COMMUNICATIOr
Category 1.1
Nr 3580
Reactor Safety
Copy N· 223
WARNING
The information contained
in this document is
communicated confidentially
by the Commission of the
European Communities
to Member States,
persons and undertakings
and should not be passed on
to third parties.
(Euratom-Treaty, Article 13, and PROGRAMME PROGRESS REPORT
Regulation (EEC) No. 2380/74
of the Council of Ministers).
July-December 1978 Programme Progress Report JRC Ispra
July-December 1978
REACTOR SAFETY
Abstract
This report is divided into two parts, (A) the main report, which is project-structured
and scientifically oriented, and (B) the summary, which is aimed at giving non-
specialized readers significant information on the R&D work of this programme.
The Reactor Safety Programme of the JRC is subdivided into six main projects:
1) Reliability and risk assessment
2) LWR loss of coolant accident
3) LMFBR subassembly thermohydraulics
4) Fuel coolant interaction and core melt-down
5) Dynamic structure loading and response
6) Structural failure prevention
The objectives of the research, carried out within these six projects, which are
subdivided into research activities, as well as their connection with the different
national programmes, are described.
The scientific and technical achievements of the different activities during the
reporting period are described in detail and conclusions are drawn for the activities
and the programme as a whole.
The planning for future activities, covering the period of the total multiannual
programme, 1977 - 1980, is given in a tabulated form. The annexed lists of the
authors and the list of the JRC publications enable the reader to obtain any further
information wanted.
Programme Progress Report JRC Ispra
July- December 1978
REACTOR SAFETY
Abstract
This report is divided into two parts, (A) the main report, which is project-structured
and scientifically oriented, and (B) the summary, which is aimed at giving non-
specialized readers significant information on the R&D work of this programme.
The Reactor Safety Programme of the JRC is subdivided into six main projects:
1) Reliability and risk assessment
2) LWR loss of coolant accident
3) LMFBR subassembly thermohydraulics
4) Fuel coolant interaction and core melt-down
5) Dynamic structure loading and response
6) Structural failure prevention
The objectives of the research, carried out within these six projects, which are
subdivided into research activities, as well as their connection with the different
national programmes, are described.
The scientific and technical achievements of the different activities during the
reporting period are described in detail and conclusions are drawn for the activities
and the programme as a whole.
The planning for future activities, covering the period of the total multiannual
programme, 1977 - 1980, is given in a tabulated form. The annexed lists of the
authors and the list of the JRC publications enable the reader to obtain any further
information wanted.
ï JOINT RESEARCH CENTRE
Ispra Establishment
Italy
Reactor Safety
PROGRAMME PROGRESS REPORT
July-December 1978 BEMÆRK
Den viden, som rummes i dette dokument, meddeles som fortrolig fra
Kommissionen for de europæiske Fællesskaber til Medlemsstater, per­
soner og virksomheder og må ikke videreaives til tredjemand. (Euratom-
traktatens artikel 13og Minersterrådetsforordning(EOF) N° 2380/74).
Hverken Kommissionen for de Europæiske Fælleskaber eller nogen,
som optraeder pa Kommissionens vegne er ansvarling for den eventuelle
brug af information, som er indeholdt i det følgende .
ZUR BEACHTUNG
Die in diesem Dokument enthaltenen Kenntnisse werden von der Kom­
mission der Europäischen Gemeinschaften den Mitgliedstaaten, Per­
sonen und Unternehmen der Gemeinschaft vertraulich mitgeteilt und
dürfen nicht an Dritte weitergegeben werden. (Euratom-Vertrag, Arti­
kel 13, und Beschluss des Ministerrates (EWG) Nr. 2380/74).
Weder die Kommission der Europäischen Gemeinschaften noch Perso­
nen, die im Namen dieser Kommission handeln, sind für die etwaige
Verwendung der nachstehenden Informationen verantwortlich.
NOTICE
The information contained in this document is communicated confi­
dentially by the Commission of the European Communities to Member
States, persons and undertakings and should not be passed on to third
parties. (Euratom-Treaty, Article 13, and Regulation (EEC) No.
2380/74 of the Council of Ministers).
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.
AVERTISSEMENT
Les connaissances contenues dans le présent document sont communi­
quées confidentiellement par la Commission des Communautées euro­
péennes aux Etats membres, personnes et entreprises et ne peuvent être
transmises à des tiers. (Traité Euratom, article 13, et règlement (CEE)
N° 2380/74 du Conseil de Ministres).
Ni la Commission des Communautés européennes, ni aucune personne
agissant au nom de la Commission, n'est responsable de l'usage qui
pourrait être fait des informations ci-après.
AVVERTIMENTO
Le cognizioni contenute nel presente documento sono comunicate con­
fidenzialmente dalla Commissione delle Comunità europee agli Stati
membri, persone ed imprese e non debbono essere trasmesse a terzi.
(Trattato Euratom, articolo 13, e regolamento (CCE) N° 2380/74 del
Consiglio dei Ministri).
Né la Commissione delle Comunità europee, né alcuna persona che
agisca per suo conto, è responsabile dell'uso che dovesse essere fatto
delle informazioni che seguono.
OPMERKING
De kennis, die in dit document is vervat, wordt door de Commissie van
de Europese Gemeenschappen vertrouwelijk aan de Lid-Staten, per­
sonen en ondernemingen medegedeeld en mag niet aan derden worden
doorgegeven. (Euratom-Verdrag, artikel 13, en het besluit van de Mi­
nisterraad (EEG) No. 2380/74).
Noch de Commissie van de Europese Gemeenschappen, noch de per­
sonen die namens haar optreden, zijn verantwoordelijk voor het ge­
bruik, dat eventueel van de hiernavolgende informaties wordt gemaakt. CONTENTS
1. Introduction 3
2. Projects 7
2.1 Reliability and Risk Assessment
2.1.1 LMFBR Whole Core Accidents Codes 7
2.1.2 LWR Core Accident Probabilistic Analysis and
Reliability Data Systems 8
2.2 LWR Loss of Coolant Accident 17
2.2.1 Loop Blowdown Investigations LOBI Project:
Influence of PWR Primary Loops
on Blowdown8
2.2.2 Basic Thermohydraulics under LOCA and
ATWS Conditions in LWR 20
2.2.3Theoretical Examination and Scoping of
Simulated Accidents in ESSOR (TESSIE)2
2.3 LMFBR Subassembly Thermohdraulics7
2.3.1 Code Development and Validation
2.3.2Sodium Boiling Studies 34
2.4 Fuel Coolant Interaction and Core Melt Down 41
2.4.1 Fuel Coolant Interaction 4
2.4.2Core Melts and Post Accident Heat Removal5
2.5 Dynamic Structure Loading and Response 6
2.5.1 Code Development and Validation1
2.5.2Material Constitutive Laws 68
2.6 Structural Failure Prevention 75
2.6.1 Fracture Mechanics
2.6.2Creep Fatigue Damage in Steels 80
2.6.3 Failure Detection in Reactor Structures
3. Conclusions 97
Annex I
Planned Activities and Important Milestones forthe
Reporting Period 100
Annex II
Planning of the Future Activities2
4. JRC Publications5
Glossary6
List of Authors7 1. INTRODUCTION
The expanding electrical energy needs in the Community can be met in the greater part only by an in­
crease in the number of nuclear power plants. This, together with the increased sensibility of the public
feeling towards the safety aspects of nuclear power installations, and its reflection on the licensing
process, has been the most general motivation for a continuous increase of the Reactor Safety R&D
activity in the JRC during this period. The present programme involves activities in the field of Light
Water Reactors (LWR) and Liquid Metal Cooled Fast Breeders (LMFBR) Safety.
The major accident to be considered in a Light Water Reactor is a severe loss of coolant due to the
rupture of the primary circuit and the consequent blowdown. Questions to be answered in this area
are: What degradation of cooling does the core have to tolerate and what is the consequent behaviour
of the cladding temperature ? Does the emergency core cooling system (ECCS) provide sufficient
compensatory cooling or does the ECCS water fail to enter the core? How does the rupture size and
position and the response of the primary circuit affect the answer to these questions? In the case of
imaginary ECCS failure and wide-spread core melting, what would be the behaviour of the core melt?
The Ispra cont