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COM (83) 300 
 
 
 
Vol. 1983/0 122 
  
 
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concernant l'ouverture au public des archives historiques de la Communauté économique 
européenne et de la Communauté européenne de l'énergie atomique (JO L 43 du 15.2.1983, 
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In accordance with Council Regulation (EEC, Euratom) No 354/83 of 1 February 1983 
concerning the openi ng to the public of the historical archives of the European Econom ic 
Community and the European Atomic Energy Communit y (OJ L 43, 15.2.1983, p. 1), as 
amended by Regulation (EC, Euratom) No 1700/2003 of 22 September 2003 (OJ L 243, 
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COMMISSION  OF THE EUROPEAN  COMMUNITIES 
COM(83)  300 final 
Brussels,  28th May 1983 
RESEARCH ACTION  PROGRAMME  ON THE DEVELOPMENT OF 
NUCLEAR  FISSION  ENERGY  (1984-1987) 
(Communication  from the Commission  to the  Council) 
COM(83)  300 final 

2 
RESEARCH  ACTION PROGRAMME  ON THE DEVELOPMENT  OF 
NüCLEAR  FISSION  ENERGY  (1984-87) 
EXPLANATORY  MEMORANDUM 
In its Communication  entitled  "Proposals for  a European  Scienti­
fic and Technical Strategy:  Framework  Programme  1984-87"(1),  the 
Commission  set out the  major goals to which this strategy should 
be geared.  Among  these goals, it  is essential  to improve  the 
management  of energy  resources  and to  reduce  energy  dependence 
if the Community  is to  face up to the  energy  challenge.  In order 
to attain  these major  goals, the Commission  recommends  that an 
approach  centred  on specific  objectives  be adopted  with a view 
to : 
"facilitating  the implementation  of the  research 
specifically  desired  by the  Member  States; 
"facilitaing  the subsequent  adoption  of action 
programmes  for implementation  by identifying  and patting 
into order the priority  needs of the  Community  and thus 
the relative  weighting  to be  given to the  corresponding 
scientific  and technical objectives;  and 
"testing  in a specific  manner  the method of making 
political  and techical  choices  as between  national, 
international  and Community  activities". 
As far as improving  the management  of energy  resources  and 
reducing  energy  dependance  is concerned,  the Commission  proposed 
to concentrate its  effort  during  the period 1984-87  on the 
following  four scientific  and technological objectives:  the 
rational  use of  energy,  the development  of renewable  energy 
sources,  controlled  thermonuclear  fusion  and the  development  of 
nuclear  fission  energy.  The broad lines of the  action programme 
on the development  of nuclear  fission  energy  that is the  subject 
of this proposal  are described  in paper COM(82)  865 final, which 
includes  in particular  the following  passage  : 
"The development  of nuclear  fission  energy  is one of the 
main ways of reducing,  through  the diversification  of 
energy resources,  the Community's  dependance  on oil. The 
continuation  of a resolute nuclear  programme  is 
therefore  an essential  aspect of European  energy  policy. 
The Community  strategy provides for  the consolidation 
and intensification  of research  activities,  in 
particular  in the  general  fields  of nuclear safety, 
health and environmental protection,  and fissile 
materials  safeguards.  The European  Parliament  has 
adopted a resolution approving  and confirming  this 
strategy  upon which the Council also  took a favourable 
position.  It should also  be recalled  that the nuclear 
(1) COM(82) 865 final. 

3 
option embraces  the development  of the entire  fuel cycle, 
including  reprocessing and fast reactors. 
It is with this in  mind that the  present  guidelines for 
Community  R&D have been drawn  up. 
"Community  R, D&D  activities  will therefore be  mainly 
directed  towards  the safety aspects, i.e. the protection 
of workers  and the general public against nuclear 
hazards.  In this  manner  Community  research can exert a 
positive  influence on the nuclear controversy, by 
providing objective information that  transcends  the 
national  dimension.  By helping to  harmonize  national 
approaches  to safety,  Community  action also assists in 
promoting  industrial  competitiveness  by reducing the 
barriers  to intra-European  trade. 
"At international  level,  there is an increasingly  marked 
tendency  to cooperate  in the general  field  of nuclear 
safety, a trend  which  is considered  extremely  favourable 
for the development  of this  energy  source  and will be 
taken into account  by Community  action. 
"The main areas taken  into consideration are reactor 
safety, the  management  and storage  of radioactive  waste, 
radiation  protection,  fissile  materials  safeguards,  the 
decommissioning  of nuclear plants, and - the  remainder 
of the fuel cycle that has already  reached  the 
industrial  stage  - certain safety  aspects  which  all call 
for Community  action". 
The guidelines  will be reflected in the  contents  of the action 
programme  to be proposed.  The sectoral research  activities 
envisaged  will generally  come under the umbrella  of the  energy 
goals, although  this rule  will not be followed systematically. 
In the event,  the objectives  pursued  by a number  of activities 
overlap  with the goal of  improving  living  and working  conditions 
as regards  both protecting health and protecting the  environment 
as implemented  essentially by the research action  programme 
health and safety.  Other  activities,  while  clearly  working 
towards  the objectives set for the  development  of nuclear 
fission  energy,  will simultaneously  attain  some of the targets 
of the goal of  promoting  industrial  competitiveness,  in 
particular  those  of eliminating barriers and of  promoting  and 
developing  new technologies. 
2. CONTENTS  OF THE ACTION  PROGRAMME  ON THE "DEVELOPMENT  OF 
NUCLEAR  FISSION  ENERGY"" 
This action  programme  is subdivided into  a number  of 
subprogrammes  that the  Commission  proposes  to distribute  between 
direct action,  which  will be carried out in the Joint  Research 
Centre laboratories, and  shared-cost  projects that  will be 
conducted  in laboratories in the  Member  States. The  reasons 

4 
that prompted  the Commission  to propose  such a breakdown  will 
be explained  case-by-case  in the detailed  proposals  for the 
different  subprogrammes;  they result  from a thorough  examination 
of the situation and of the current capacities Of  Community 
research and national research in the  Member  States. The  JRC's 
programme  of direct-action research for the period  1984-87  will 
be presented  and discussed in its entirety within the various 
Community  bodies,  but some aspects  of that  programme  - which 
form an integral part of this action  programme  on the 
development  of nuclear  fission  energy  - must clearly  be assessed 
from this angle,  in particular as  regards  their overall  budget 
and their  interdependence  with the other  aspects  of the action 
programme  that are  proposed  as shared-cost  projects. 
The action  programme  on the  development  of nuclear  fission 
energy comprises  the following aspects: 
1. Reactor  safety  activities 
The aims pursued  by some of these  activities  overlap  with those 
covered  by the goal of  improving  living  and working  conditions, 
namely improving  safety, protecting health and protecting the 
environment.  Part of  these  activities  will also contribute 
towards  the goal of  promoting  industrial  competitiveness,,  in 
particular  the objectives of  removing  and reducing barriers and 
of promoting  and developing  new technologies for conventional 
industries. 
1.1. Direct action on reactor safety  (1984-87) 
This is the largest of the  JRC's programmes.  The research 
conducted  is more often than not confirmatory in  nature  and is 
intended  to back up the  work of the licensing authorities  with 
experiments  and detailed theoretical  analyses  and to  meet the 
needs of nuclear  power  station  operators  and nuclear  component 
manufacturers.  In addition to certain horizontal  activities  on 
topics of  concern  common  to all reactor  concepts,  the projects 
relate essentially to  light water  reactors and liquid-metal fast 
breeder  reactors. 
1.2. Programme  of shared-cost  action on reactor safety  (1984-87) 
The field  covered  and the objectives are identical to  those  of 
direct action on reactor safety,  while  the projects  proposed 
will either  supplement  or back up those  to be conducted  under 
direct action and  will be closely integrated  with the different 
national  programmes  being pursued  at the centres  where  they will 
be carried out. 
1.3. Implementation  of the Council Resolution of 22 July 1975 on  
technological  problems  of nuclear safety 
This activity  began  in 1976  with the entry in the research 
budget of a budget  heading  covering  staff  expenditure  (for four 
Category  A, two  Category  B and two  Category  C staff).  The aim of 
this activity  is to carry out  comparative,  analytical and re-

5 
view studies,  mainly  concerning  research coordination  and the 
harmonization  of methodologies,  codes and safety  standards  for 
both the thermal  light water  reactor  and sodium-cooled  fast 
breeder  reactor  concepts. 
In 1980, the Council  agreed  upon a Commission  proposal  to 
supplement  this activity  with a contractual  component  designed 
to provide  financial  support  for comparative,  analytical  and 
review studies  on codes and standards  for fast reactors. 
This activity  will be continued  during  the period 1984-87  on 
the same level as in the  past. 
2. Direct action  on plutonium  fuels und actinides research  
(1984-87) 
This programme comes  under the umbrella  of both fast reactor 
fuel development  and more  fundamental  research  on actinides.  It 
is to be  carried  out mainly in the  specialized laboratories  at 
the European  Institute  for Transuranic  Elements,  Karlsruhe. 
3. Activities  relating  to radioactive  waste 
Although  specific  to the  objectives  pursued  for the  development 
of nuclear  fission  energy,  these  activities  make an extensive 
contribution  to those adopted  for the  goal of improving  living 
and working  conditions,  namely  improving  safety, protecting 
health and protecting  the environment. 
3.1. Direct action  on the management of  radioactive  wastes  
(1984-87) 
This programme  focuses  essentially  on the  problems  that arise  in 
the conditioning  and interim  or final disposal  of radioactive 
waste, and both theoretical  and experimental  studies  will be 
carried out in  order to assess  waste management  procedures  from 
a safety  angle. 
3.2. Programme of  shared-cost  action  on the management and  
disposal  of radioactive  waste (1985-89) 
A second  five-year  (1980-84)  programme of  shared-cost  action  is 
currently  in progress.  This programme is  closely  coordinated 
with the activities  carried  out by the JRC in the same  field and 
has been thoroughly  integrated  with the national  programmes 
since its inception  in 1975. On  completion  of the  current 
programme at the end of 1984, the  Commission  will propose,  in 
accordance  with the 1980-92  plan of action in the  field of 
radioactive  waste,  that work be  continued  in this area. The 
broad lines of this new programme  will comprise  on the one  hand 
the characterization  of conditioned  wastes  with a view to its 
disposal  and the  improvement  of the  processes  used, and on the 
other hand the study of the  performance  of the  various 
geological  storage  options  and their confinement  methods and 

6 
the assessment  of their safety, Although  the expiry date  of the 
current programme  does not make it possible  to begin the third 
radioactive  waste programme at the  same time as the 1984-87 
action programme, it  nevertheless  forms  part of the  latter,  and 
account  should  be taken of this fact as far as its  links with 
the direct  action  proposed  in section  3.1 above are concerned 
and as regards  its financial  repercussions  on the  action pro­
gramme during  the period  concerned  (1985-87). 
4. Direct action  on the  safeguarding  and management of  fissile  
materials  and support  for the  Safeguards  Directorate  
(1984-87) 
The continued desire  to reinforce  measures  for the  safeguarding 
and management of  fissile  materials underlines  the need for a 
sustained  research  and development  effort.  In close coordination 
with the Euratom  Safeguards  Directorate,  the national 
laboratories,  those in charge of nuclear plants  and the  IAEA, 
the JRC proposes  to increase its contribution  to this effort. 
The proposed  programme is  aimed at developing various safeguards 
techniques  for application  in the  main types of nuclear plant. 
These techniques  will help in the  quantitatives  determination  of 
nuclear material,  in their identification,  confinement  and 
management. The  related  activities  will also help  in developing 
a system  ofmanagement of the  information  originating  from 
utilities  and from inspection operations. 
Finally the studies  are concerned  with the development  of 
methodologies  for the  parametric analysis  of the  performance  of 
the techniques  of contrôle  in different  types of plants  or in 
the fuel cycle. 
5. Programme of  shared-cost action  on the  decommissioning  of  
nuclear plants  (1984-88) 
This programme is the  logical  follow-up  to that currently  in 
progress  on the  decommissioning  of nuclear  power  stations.  Its 
scope is wider than the latter and its main aim is to  make 
available  effective  solutions that  are capable  of ensuring  the 
safety and protection  of man and his  environment  against  the 
potential  risks  associated with  the decommissioning  of nuclear 
plants. The financial  repercussions  of this programme to be 
taken into consideration  in the  action  programme  have been 
adjusted  to make allowance  for the  fact that the present 
proposal covers  a period  of five years. 

6 bis 
PARTICIPATION  TO INTERNATIONAL  PROJECTS  OR TO RESEARCH  PROGRAMMES 
IMPLEMENTED  IN MEMBER  STATES 
The complexity  of research  problems  in the  nuclear  field, the increasing 
costs of the  necessary  installations  and the  very specific  competences 
to be mustered for  their solution,  lead to the  internationalization  of 
nuclear research  and to the  development  of scientific  and technical 
relations  between  the Member  States and Third Countries pursuing  policies 
of nuclear  energy for  peaceful  use. 
The different  sub-programmes  proposed  within  this research action 
programme  leave open to the  Commission  the possibility  to participate 
to international  research projects  and to  research  programmes  implemented 
in Member  States when this participation  is useful to the  successful 
implementation  of the  proposed  sub-programmes.  According  to needs this 
participation  could take  the form of financial  contribution  or exchange 
of information  and results. 
This type of collaboration  has already  been used in the  past for the 
current programmes.  Framework  agreements  alreday  existing  between  the 
Commission  and specialized  organizations  in Third Countries  might be used. 
RESOURCES 
The proposed  budgets  for each of the  seven headings  of the 
action programme are set out in the  following table. Part  of 

7 
the resources allocated to several  headings  will cover  to a 
certain  extent -  which  will differ  according to the  case in 
point -  expenditure  on goals and objectives to  which  the 
Commission  attaches  priority  but which  do not relate to the 
specific  aim of developing nuclear  fission  energy,  nor even the 
energy goal. 
The amounts  set out in the following table are  expressed  in ECU 
at constant  mid-1983  prices. The  final programme  proposals  will 
comprise  figures that  will be updated  in line with inflation 
forecasts and  with due regard to the timetables for the 
commitment  of appropriations. 
The breakdown  of resources  between  the different  sectors and 
types of activity  and the  total budget,  which amounts  to 477.5 
million  ECU, are  compatible  with the guidelines set out in 
document  COM(82)  865 final. 
BUDGET ESTIMATES  (1983 PRICES) 
Action programme  constituents  million  ECU (1) 
1.1. Direct action on reactor safety 192.2 
1.2. Programme  of shared-cost  action on 
reactor safety  (1984-87)  68.0  81.3(4) 
1.3. Implementation  of the Council Resolution 
of 22 July 1975 on technological  problems 
of nuclear safety 3.3 
2. Direct action on  plutonium  fuels and 
actinides  research  (1984-87)  65.7 
3.1. Direct action on the safety of nuclear 
materials  (1984-87)  48.9 
3.2. Programme  of shared-cost  action on the 
management  and disposal of radioactive ,5s 
waste (1985-89)  43+pm(2)  75 or 100 
4. Direct action on the safeguarding and 
management  of fissile  materials and 
support  for the  Safeguards  Directorate 
(1984-87)  45.4 
5. Programme  of shared-cost  action on the 
decommissioning  of nuclear plants 
(1984-88)  11(3) 
TOTAL  477.5+pm 
(1) 
(2) 
(3) 
(4) Mid-1983  prices. 
For the  first  three years  of the  third programme  and the 
final year of the current  (second)  programme. 
For the  first  four years  of the  programme. 
Figures in actual ECU taking into  account  inflation  (7 % per 
year) during the execution of the  programme.  This figure 
will appear  in the formal proposal to be  submitted  to the 
Council.  (Note  5 : see  next page). 

8 
(5) As point (4) above, but figures  for 5 years. The high alter­
native (100 MECU)  corresponds  to the  case in which a pilot 
installation  would be decided.  In this case the figure 
(1983 value) corresponding  to the  period covered  by the 
action plan (43 MECU)  should be increased  (+ pm). 
SYNCHRONISATION  OF THE  CONSTITUENT PARTS  OF THE  ACTION PROGRAMME 
All the constituents  of the  action programme,  with the exception 
of two, cover the period 1984-1987.  The two  exceptions  are the 
following  : 
- Constituent  3.2. Shared-cost  action  on the  management  and 
disposal  of radioactive  waste,  which is a part of the  "Radio­
active Waste Management" Sub-Programme. 
The present  programme  will terminate  at the end of  1984 and 
the next  programme  will start at the  beginning  of 1985. 
- Constituent  5. Shared-cost  action  on the  decommissioning  of 
nuclear  installations. 
The present  programme  will terminate  at the end of  1983 and 
the next  programme  will cover the period 1984-1988. 
It is the  intention  of the  Commission  to unify the planning  and 
the execution  of the  action programme  by synchronizing  the 
different  subprogrammes. 
The Commission  reserves therefore  the right to submit for 
revision  all the constituents  of the  action progamme  at the end 
of 1986, at the  same time as the  reexamination  of the JRC 
programme,  which contains  an important part  of the  action* 
programme  on the  development  of nuclear  fission  energy. 
1. SUB-PROGRAMME  "SAFETY  OF FISSION  REACTORS" 
This programme  covers both  Light Water  Reactor  (LWR)  Safety and 
Liquid Metal Fast Breeder Reactor  (LMFBR)  Safety. 
In the description  of objectives  no distinction  will be made 
between JRC and  Cost shared  activities.  However,  the activities 
will be identified  separately  for each type  of action. 
JRC activities  bearing  a star are discussed  in the  frame of the 
SUPER SARA  replacement  programme.  In fact, the programme 
outlined  hereunder takes  into account  the decisions  to abandon 
the SUPER SARA  Project  and it is in  line with the outcome  of the 
orientation  Council debate  of 10.3.1983  on the  future  activities 
of the Joint Research Centre. 
Programme  objectives  and activities  will be discussed  under two 
broad headings, i.e. accident prevention  and accident  analysis 

9 
control  and mitigation, although  some  activities  give contri­
butions to both 
General  criteria  for the  selection  of topics  have been : 
- to maximize  effectiveness of  Community  effort  by selecting  a 
limited number  of important areas  where Commission  can best 
stimulate  coordination and collaboration  amongst  national 
programme  ; 
- searching for  common  interest  of Member  States, avoiding 
design-specific  issues. 
I.A. Light  Water  Reactor Safety 
l.A.l. Objectives 
Within the  Member  Countries of the  European  Community,  by tne 
end of 1981, a  total of about  40 LWR nuclear  power  plants iave 
been in operation, and 30 plants  have been under constru' .ion. 
The corresponding  electrical  power  generation capacity  .nounts 
to 40.000  MW for those already in operation, and an additional 
37.000 MW for those at present  under  construction. 
Although the  existing  plants  show a satisfactory  availability, 
and operation in  above-average  safety conditions, reactor safety 
research  programmes  must continue in order to  ensure  that the 
safety margins  built-in  today  be further evaluated and 
quantified.  The knowledge  increase being acquired  will at the 
same time make an important contribution to the  development  of 
reactor  technology,  particularly  to the safety  system  desing. 
In the area of accident prevention, the objective of the  efforts 
is a continuous increase in design and  fabrication  quality  of 
the various  components  and systems,  with the aim of increasing 
the operation  reliability.  As a consequence,  an important 
contribution  is provided to the operational safety and  economy. 
The major  effort  of the  Commission  in this area is  coming  from 
the following actions : 
- Risk and  Reliability  Assessment  : 
Methodologies  are being developed with the aim to  identify, 
model and analyse the accident  sequences,  and to investigate 
the reliability  of components  and systems.  This action 
includes  the collection  of data and information  from operating 
power plants in the  framework  of a data  bank system  (ERDS  -
European  Reliability  Data information  System). 
- Human  Factors and  Man-Machine  Interaction : 
Several  meetings  on this topic have been organized by the  Com­
mission during the past with the  participation  of experts  from 

10 
US and Japan.  For the  Commission  nuclear  programme,  this acti­
vity represents a new research area; within the  Member  coun­
tries, corresponding  actions are limited and rather dispersed. 
The objectives of the  proposed  actions focus on the  improve­
ment of the basic  knowledge  on operator  behaviour  taking into 
account  the most important  influencing factors  (environment, 
special  conditions, etc.). 
The implementation  of the  ERDS will facilitate  the collection, 
processing and use of  data relating  to the  human  reliability. 
- Integrity of  Components  and Systems 
The investigation of materials, *  'ie detection of flaws and the 
integrity  of structures represen an  important  area of 
research in  view of accident pre-ention. 
The long  term objectives are to establish a systematic ap­
proach which  allows, by relying on different  types of varia­
bles, to determine  the residual  life time of the structures. 
More recently,  some EEC member  countries  have brought  to the 
attention  of the  Commission  the desire to  dipose  of a medium 
size shaking  table for seismic effect studies. This proposal 
will be analysed to better  understand  its technical merits and 
overall  feasibility. 
In the area of accident analysis, control and mitigation of  
accident  consequences , the Commission  intends to  improve  the 
knowledge  of mechanisms  governing  the accident evolution.  Mer­
ging the  experimental  and the analytical research is an  essen­
tial goal to  ensure  that the results of  expensive  experiments 
are reflected in the  improvement  of models  and codes  used for 
the reactor safety analysis. 
The availability  of experimentally  verified  computer  codes  to 
potential  code users  (reactor  vendors,  licensing authorities and 
utilities)  should  enhance  a progressive  harmonisation  of safety 
analysis  within the  European  Community,  and should at the  same 
time provide the  means  necessary  to satisfy  a certain  number  of 
quality  assurance  criteria.  The employment  of both large  in-pile 
and out-of-pile  installations,  and of  skilled  multidisciplinary 
teams require the  widest  possible international collaboration. 
The objectives of the actions  proposed  deal mainly  with areas 
which play an  important  role for the  realistic  evaluation of the 
course and consequences  of accidents. The various subjects  areas 
follows : 
- Investigation of off-normal  behaviour  of reactor core and  
cooling  system  (core temperatures  below  1200 C). 
These studies  cover  small and large  breaks  and also transients 
in the primary  and secondary  cooling  circuits  which  do not 
substantially  damage  the fuel elements.  The principal aim of 

11 
these studies is the  development  of physical  models  and of 
computer  codes  for separate  effects  and for the  complex 
interactions  between  various  phenomena  during the accident 
scenario of  temporary  loss of cooling of the core. 
- Investigation of  severe  accident  behaviour  of reactor core  
and cooling  system  (core temperatures  above 1200°C) . 
The aim of  these  investigations is the analysis of  mechanisms 
and phenomena  which are of  primary  importance  during the 
course of an accident and  might have the potential to  cause 
loss of fuel integrity  and, as a  consequence,  the release of 
fission  products  and hydrogen. 
In the framework  of this activity,  the Commission  proposes  to 
make available to the  Member  Countries the  competences 
acquired in executing the  SUPER SARA programme  in the past. A 
close cooperation with all laboratories of the  Member  States 
will be established in order to  make best use of  existing 
means and competences. 
- The reactor outer  containment  phenomena  during  severe  acci­
dent conditions. 
Internal  pressure and  temperature  loading of the outer 
containment  are generated  in hypothetical accident scenarios 
by gaseous  products  or vapour  released  from the reactor 
primary/secondary  loops and by reaction  products  between 
molten core material and concrete. The evolution in  time of 
this loading  depends  strongly on the postulated accident 
scenario and is in  most of cases  plant  specific. 
The objectives of the  Community  program  are therefore to 
increase the  understanding  of phenomena  which  are common  to 
all LWR reactor designs and  have an important  impact  on risk 
evaluation,  such as: the  distribution,  combustion  and recom­
bination  possibilities  of hydrogen  in a comples  environment  as 
well as the  fission  product  transport and chemistry. 
External loading of the outer  containment  could be  generated 
by air  craft crash, gas cloud explosions, and seismic  effects. 
The objectives of  Community  efforts  are primarily concentrated 
on the understanding  of the potential  danger  of gas cloud 
explosions and the analysis of possible techniques to  prevent 
its effects. 
- The dispersion of  fission  products  in the  atmosphere 
This problem  deserves  particular  attention in  Europe  where  the 
individual  states are  relatively  small and the population 
density high. 
Therefore, the  consequences  of a large hypothetical release of 
fission  products  will under  certain conditions  have an impact 
on more than one country. 

12 
The identified  Community  task in this  area is to promote  a co­
herent approach  of calculation  model development  and verifica­
tion which  should  also consider the probabilistic  aspect  of a 
series of phenomena.  It is in addition  foreseen  to join Euro­
pean laboratories in a  common  experimental  exercise to 
investigate  fission  product  transport  phenomena  over large 
distances. 
I.A.2. Brief description of  proposed  activities  
1.A.2.1.Reliability and  Risk evaluation 
- Direct action 
The J.R.C.  action is  centered  on two  main activities,  i.e. 
- the creation of viable information  system  on reactor  opera­
tion: the European  reliability  data system  (ERDS).  The aim 
of the present  programme  is to bring all the  ERDS with its 
four data banks  into full operation. 
- the development  of methodologies  for probabilistic risk 
assessment  and their application in identifying,  modelling 
and analysing LWR accident  sequences  taking into  account  the 
timing of  events,  the operator  intervention and 
uncertainties  propagation. 
These activities  may be  extended  in developing  techniques 
and models  that make possible simulation (in real  time or 
faster) of the various  phases  of accidents. 
* Profitable use can be  made here of fast  running  thermal 
hydaulic  computaion  tools as  were developped  for SUPER SARA. 
- Shared  cost action 
In order  to support  the programme  mentioned  under  a) and to 
get more and more organisations involved in assessing 
advantages  and disavantages  of the probalistic risk 
assessment,  a series of  benchmark  exercises  will be organised 
on subjects to be  agreed  e.g. procedures  to construct  event 
trees, common  cause/mode  failure,  probability of  failure  of 
structures, etc.... 
1.A.2.2.Human factors and man  machine  interactions 
- Direct action  : none proposed. 
- Shared cost action : 
The programme  is divided into two  main areas  : 
- the collection and analysis of relevant  human  behaviour  data 
including  informations  available in  non-nuclear  activities  ; 

13 
- the modelling  of man  behaviour,  the comparison  of different 
models and analysis of their  suitability  for probabilistic 
risk assessment  (PRA) as well for their use for plant 
design and operation. 
Close working  relationships  will be established  with different 
organisations e.g.  Halden,  EPRI,  NCR, the  utilities,  non-
nuclear industries, etc.... 
1.A.2.3. Integrity  of components  and systems 
- Direct action 
The activities  of J.R.C.  concentrate  on the following  main 
topics : 
- evaluation of the effectiveness of non destructive 
examination  (NDE) techniques  including the  PISC II programme 
representing a  comparison  exercise of NDE  techniques 
conducted  on behalf of  OECD/NEA  and involving laboratories 
of 15 countries. 
An extension to include austenitic  welds  inspection 
* techniques  is under discussion as well as an exercise to be 
conducted  on irradiated materials in the JRC  ADECO 
facilities  using real scale  samples  coming  from power 
stations  which  are being  dismantled. 
- Primary  circuit  components  life prediction using 1 to 5 
scale models  of PWR vessels.  These  tests are  expected  to 
check the validity  of combined  modelling  and non destructive 
inspection  techniques  when determining  the  life expectancy 
of structures. 
* - Feasibility  study  and possibly  design  for a medium  size 
shaking  table. 
- Shared cost action 
The cost-shared  program  is expected  : 
- To help national laboratories in  performing  so called 
parametric  studies in  support  of the  PISC activities. 
These studies  should  better characterize the NDT 
equipments  and help in assessing the  validity  of the NDE 
techniques  in view of their use in nuclear  power  plants. 
- In the  field  of fracture  mechanics  the sources  and effects 
of residual stresses  will be investigated and contribu­
tions for the  numerical  analysis of elasto-plastic 
fracture  mechanics  will be made. 
1.A.2.4.Reactor  core cooling  system  off normal  behaviour 
investigations  (fuel temperature  < 1200°C) 

14 
- Direct action 
Tho 3Ladies  with the integral  system  LOBI facility  built  and 
e:-_jloiceu  at present  in cooperation  with the BMFT are aiming 
at. the investigation of the  thermohydraulic  behaviour  of a PWR 
cooling  system  during large and small  breaks  and special 
transient conditions.. Principal  activities  are : 
- thermohydralic  analysis of the physical  phenomena  occuring 
in the core (including e.g.  critical  comparison  of alterna­
tive emergency  core cooling and  decay  heat removel  (DHR) 
systems). 
- Application of large  system  codes  for test prediction and 
analysis calculations, and  assessment  of these codes  in the 
framework  of this  activity. 
* LOBI experience  in the  area of code application and  assessment 
shows that there  is a need for an  extension  of the  independent 
assessment  of large  computer  codes  including  improvement  of 
physical  models  on tu3 basis of prediction calculations and 
thermohydraulic  analysis of the results and the  development  of 
a plant  code analysis as a tool to  facilitate  the assessment 
process. 
- Shared cost action 
The shared  cost activities  are a logic continuation of the 
existing  programme  and complementary  to the  J.R.C.  activities. 
The concern  basic studies on small scale  experiments  and 
include detailed evaluations leading to the  development  of 
models for large  system  codes. 
Examples  of these  studies are : basic  heat transfer studies in 
the tv<o phase flow regimes,  coolant  flow patterns in a variety 
of conditions simulating the coolant  behaviour  in different 
plans of the  primary  and secondary  loop systems. 
1.A.2.5.Reactor  core and cooling  systems  under sever  accident  
conditions  (fuel  temperature  > 1200 C) 
- Direct action 
* The chief aim of the  SUPER SARA programme  was to obtain an 
understanding  of the key  phenomea  in a severe  accident 
scenario involving  core uncovery  with subsequent  fuel damage 
and fission  product  release and transport. The presently 
planned  activities  are directed  towards  the same goal but are 
essentially  limited to : (i) analysis of available  in-pile 
data, (ii) development  of models  respectively  computation 
tools, (iii) specific  experimental  (out-of-pile)  support. 
Thermal hydralic analysis  will focus on core uncovery  and 
-reflood  transient and involves  modelling  of : transient two 
phase flow, convective  heat transfer in the  uncovered  (vapour) 

15 
region,  effects  of radiation  and chemical  reaction. 
The phenomena  to be  modelled  for the  fuel are fuel rod and 
clad deformation,  liquefaction  and relocation  as well as clad 
and fuel fragmentation  phenomena.  Tests in support  of model 
and code development  can be  conducted  on existing  installa­
tions which are designed  to cover an unusual  wide pressure 
range. 
In the field of fission  product  release  a deep study and 
assessment  of the  world effort  on modelling  and code 
development  is planned. 
- Shared  cost action 
The aforementioned  direct-action  programme  has to be  closely 
associated  with the planned  cost shared  activities  (covering  a 
variety of out-of-pile  tests and model development  tasks) in 
this field. It is  further necessary  to have access to results 
provided to establish  collaborations  with : 
- the Swedish  activity  Marviken  V 
- the US/DOE  sponsored  activities  LOFT and Clean-up TMI 2 
- the US/NRC  sponsored  activities  PBF, NRU,  ACRR-Sandia  and 
possibly at a later time with  : 
- the Canadian  program  NRX/NRU. 
The Commission  will also explore  possibilities  of parti­ 
cipation in integral  test programmes  performed  in Europe 
(PHEBUS). 
In addition,  the Commission  proposes its  participation  in 
separate  effect testing  programmes  and related  analysis  work 
in the areas of material  reactions  (chemical  and physical 
processes),  the formation  and coolability  of fuel debris, the 
likelihood  and effects of steam explosions,  the potential  melt 
attack on pressure  vessel and base-mat,  etc. 
It is expected  that from these  studies  guidance  is obtained to 
preserve or to recover the reactor core in a stable situation 
even in those cases  where a large power-cooling  mismatch  has 
temporarily  occurred. 
The activities  of fission product  release/transport  and the 
aerosol behaviour  studies are related to the  whole chain of 
events : 
- the fission product  release  from fuel 
- the physico/chemical  effects  during  fission  product  trans­
port from the primary  circuit to the  containment  and the 
phenomena  occuring  in the  containment. 

16 
1.A.2.6.The  reactor  outer containment  phenomena  during  severe  
accidents conditions 
- Direct action 
* The J.R.C.  disposes  of a large reservoir  (100 m3) to contri­
bute in the  hydrogen  combustion  studies. Possibly  the ESSOR 
outer containment  could also  be made davailable  to analyse  the 
distribution  of hydrogen  and other gases. 
- Shared cost action 
The activities  foreseen  in cooperation  with national organisa­
tions are both analytical  and experimental. 
- Combustion  processes  will be studied  to determine  flamability 
and explosion  limits  for multiple  component  systems  and 
particular  attention  will be devoted  to the  deflagration  to 
detonation transition  criteria. 
- Techniques  will be developed  to mitigate  the effects  of 
hydrogen  combustion  using either controlled  recombination  with 
oxygen or other techniques. 
- Always in the  field of distribution  and combustion  processes, 
studies  will be continued  to determine  outer containment 
external loading  by gas  cloud explosions  and the  response  of 
reactor  containment  structures. 
1.A.2.7.The  dispersion  of fission  products  in the  atmosphere 
- Direct action 
None proposed. 
- Shared cost action 
The Commission  participated,  with da small effort in the  past, 
to programmes  which should help in assuring radioprotection  to 
the population  under accidental conditions.  \ 
This effort is planned to be increased  and particular atten­
tion will be given to research  in the  areas of definition  of 
the accidental release,  the study of special effects  like the 
dispersion  of products  over sea, the  development  of dispersion 
models and their verification  in small and large distance 
tests to be conducted  by collaborative  field trials. 
1.A.3, Resources 
See table  "Summary  and articulation  of action programme on the 
development  of nuclear  fission  energy". 

17 
1.B. Fast Breeder  Reactor  Safety 
l.B.l. Objectives 
Most of the Member  States of the  Community  have devoted 
substantial  effort  to the  development  of Liquid  Metal Fast 
Breeder  Reactors  during the past 25 years.  Very large  financial 
efforts  have been devoted  to this development  which to-day  still 
accounts  for approx.  20% to  total R + D  expenditure  in the 
energy sector. The  Community's  technical  achievements  are 
unmatched  in any other region of the  world  : several  expermental 
reactors  dand prototypes  have been succesfully constructed and 
operated  and one large  demonstration  station  (Super  Phenix,  1300 
MWe) is nearing  completion  (1984). 
The broad  aim in the selection of topics for the  Community 
1984-1987)  programme  has been the consistency  with the 
objectives of the Council Resolution of  18/2/1980  concerning 
fast breeder  reactors (*). 
The above  mentioned  Council Resolution underlines the  importance 
of the fast breeder  option for the future  energy  supply of the 
Community,  stresses the  importance  of continuity in the  effort 
of developing the  system,  reaffirms the  paramount  importance 
ofsafety  as an objective of the  development  effort  and calls 
upon the Community  to lend  support  for the  above  objective. 
Under the heading  of accident prevention, it should  first  of all 
be mentioned  that the  effort  on development  of probabilistic 
risk analysis,  human  factors and  man/machine  interaction  covered 
under the LWR section, are generally relevant to  LMFBRs  and are 
therefore not  repeated  here.  The topics  addressed  more 
specifically  in the  LMFBR  section are : 
- Instrumentation,  control and protection. Its  broad  objective 
is to improve  the treatment  of information originated in  vital 
parts of the  system,  and particularly  in the very  compact 
core, in order to  permit  the monitoring  of the state of the 
plant for operator information and eventually for  automation 
of corrective action. 
- Integrity of  components  and structures, and related studies on 
material properties. The long  term objective is to arrive at a 
systematic  approach  permitting the correct  assessment  of the 
life time of structures taking into  account  the specific 
service  loadings, materials and  environment  of LMFBRs. 
It must be noted  that the  LMFBR  structures are  made of thin 
walled stainless  steel working  at high  temperature  and are 
therefore substantially different  from those used in LWRs which 
are thick,  made in great part of  ferritic  steels and  work at 
lower temperature. 
(*) O.J. N° C  51/5 of 29/2/1980. 

18 
Thus design and calculation  codes as well as  non destructive 
methods  of inspection  must take into account  phenomena  and 
material properties for  which  experience in Light  Water Reactor 
components  design, construction and operation is not necessarily 
sufficient  or relevant. 
Under the heading  of accident analysis, control and mitigation, 
the objectives are to participate in solving  specific 
thermo-hydraulic  problems  which  are very  important  during the 
initiating  phase  of the accident. A  significant  effort  will be 
devoted,  like in the past, to the  study  of the  most severe  and 
unlikely  accidents involving  severe  damage  of the core.  However, 
increased  emphasis  will be given to a  more realistic  description 
of the different  phases  of potentially  severe  accidents. This is 
expected  to lead to a reduction of conservatism in the 
evaluation of  mechanical  energy  release and it coul in general 
show that the reactor  behaves  much more benignly  than now 
postulated. The following topics are included  under  this 
heading  : 
- Reactor  core and cooling  systems  in off-normal conditions 
- Severe accident danalysis 
- Integrity of structures  under dynamic  loadings 
- Outer containment  in accident conditions. 
I.B.2.  Activities 
1.B.2.1.Instrumentation,  control and protection 
- Direct Action  : none proposed. 
- Shared  Cost Action  : 
Sensor Improvement. 
Improvement  of instrumentation  reliability  and application to 
fault identification  and location by  : 
- development  of sensors for a  LMFBR environment  using novel 
or diverse  measuring  principles as well as novel 
transmission  means, 
- grouping  of instruments  into single  easy-to-handle  probes. 
Computer  base signal processing techniques  & application 
Apllication  of computer  based  signal processing techniques 
(e.g. pattern recognition) and application to  : 
- thermal  and accoustic noise analysis in  sodium, 
- improvement  of discrimination  between  faults  and artifacts 
in accoustic and  eddy current inspection of reactor 
components , 

19 
- automation  of failed  fuel location using delayed  neutron 
detectors, 
- reactivity  and subassembly  state monitoring. 
System Design 
Development  of system  design  concepts  that reflect  general 
trends towards  distribution  control,  more elaborate control 
structures  and increasing  levels  of monitoring and  meet 
requirements  for demonstrable  reliability,  safety,  speed  of 
operation and  improved  plant  evailability. 
1.B.2.2.Integrity of  Components  and Structures 
- Direct Action : 
The JRC  activities  in this field  are concentrated on : 
- characterisation of reactor materials  (under  various  strain-
rates, temperature  and irradiation  conditions), in particular 
creep-fatigue  tests, 
- development  of constitutive  equations  with the introduction of 
material  damage  models, 
- fracture  mechanics  tests on  different  shaped  specimens  irra­
diated at different  fluences for the evaluation of  irradiation 
damage. 
Shared Cost Action 
- Validation of constitutive  equations  by experimental tests 
for shapes,  mdaterials (including  weldments)  using loading 
combinations  which  are representative of  real operating 
conditions of  fast reactors. 
- Service  life prediction exercises for selected austenitic 
steel components  e.g. a pipe  elbow  and ferritic  steel 
component,  e.g. tubing section for  boiler  use. 
- Structural defect propagation 
Tests on large  specimens  and model  structures (including 
weldments)  subjected to  typical  reactor loading  histories  : 
biaxial  loadings,  combined  membrane  and biaxial  loadings, 
combined  primary  (mechanical)  and secondary  (thermal, 
residual)  stressing,  cyclic  loading. 

20 
1.B.2.3.Reactor  core and cooling  systems  in off-normal condi-
tions 
- Direct Action 
An existing well  equipped  sodium  loop is available  which  will 
be used for the following  activities  : 
- Measurement  of the  sodium  boiling  characteristics at  steady 
state and transient  mass flow conditions and  thermal  noise 
analysis  with the 12-pin  grid/wire  spaced  and full length 
test sections  (this  part of the  programme  will be concluded 
at the beginning  of 1985). 
- Simulation of  decay heat removal  from subassemblies  : the 
specific  phenomena  to be investigated  will be the  heat 
transport by natural convection and its  limit. 
This study  has validity  for all  fast reactor  designs  and is 
complementary  to the proposals discussed hereafter. 
- Shared Cost Action 
- Sodium  coolant  thermo-hydraulic  studies :  Improvement  to be 
modelling of natural convection and  sodium  boiling  in 
transient  and shut-down  conditions. Attention  will be paid 
to description of the  heat path between  the core and the 
intermediate  heat exchanger  and to the  temperature  field in 
the upper plenum. 
- Transient  fuel behaviour  (in-pile  experiment) 
. Transient  fuel behaviour 
It is proposed  to perform  slow overpower  transients in the 
HFR reactor at Petten in  which  similar  experiments  had 
already  been carried out for loss of flow conditions. HFR 
is particularly  suited for single pin transients  with 
power doubling  times  of 1 to 10 sec. The reactor has the 
possibility  to precondition  fuel pins over a certain 
period at  nominal  power  before the transient is  initiated. 
1.B.2.4. Severe Accident Analysis 
~ Direct Action 
At present available  computer  codes  deal with the initiating 
events up into the early transition  phase (e.g. EAC/JRC)  and 
with the later phases  of the accident scenarios (e.g. 
SIMMER/NRC).  In both the early and  later phases  of the scenarios 
complicated flow situations  occur involving  multicomponent  / 
multiphase  fluid dynamics.  The present project  aims at improving 

21 
the capabilities  of both EAC and  SIMMER  to achieve  greater 
realism in accident simulation  and consequence  evaluation. 
The theoretical  model development  will be supported  by an 
experimental  validation  programme  with simulant  and real reactor 
materials. 
An important  effort  will be devoted  to the  experimental 
investigation  and modelling  of specific  aspects  of accident 
scenarios,  such as plugging  and freezing  phenomena,  fuel coolant 
interactions,  coolability  of debris bed under post accident 
conditions,  formation  and cooling  of molten  pools,  thermomecha-
nical load on core catcher structures. 
To this  aim the  following  activities  are planned  : Continuation 
of the in-pile  PAHR programme  coordinated  and funded  by the JRC 
to study the coolability  of debris  beds: the in-pile  tests  will 
be performed  in the BR2 (Mol) and in  Melusine  (Grenoble) 
reactors. 
- Out-of-pile tests  in the  multipurpose  FARO facility  where 
100 Kg U02 can be  melted  and released  in different test 
sections,  to investigate plate erosion  by U02  jets, plugging 
and freezing  phenomena in  channel  and cluster  geometry, 
thermomechanical  load on structures,  fragmentation  and 
settlement,  large mass fuel-coolant interaction. 
- Cost shared  action 
- fuel post-failure  phenomena  (in-pile  tests) 
The simulation  of two  types of accidents  is proposed  : a 
loss of heat sink and subassembly  accident. 
The whole  accident  sequence  will be investigated starting 
from the cooling perturbation,  up to the  melt down of fuel 
elements,  and the  behaviour  of molten  material. Particularly 
in case of a subassembly  the behaviour  of a molten  pool and 
its cooling potential  will be of  main concern. 
It is foreseen  to perform  these experiments  in the BR2 
(CEN-MOL) and SCARABEE  (CEA-Cadarache)  reactors. 
The funding  requested  for the  in-pole  experiments  covers  the 
cost of feasitility  studies  which are necessary  for the BR2 
and B-art  of the SCARABEf programme and the  execution  of some 
SCARABEE  experiments  during  a two  years  period. 
- Molten  material  motions  and interactions 
Separate  effect  type investigations  will be concluded  as a 
complement  to direct action  activities  : 

22 
. Expermental  investigations  of specific  molten  material 
problems,  e.g., ejection frc;.  ' core, interactions with 
structures . 
. Contribution to  code development  and validation for multi­
phase, multicomponent  phenomena  treatment. 
Activities  will also be started concerning 
- Fission  product  release  from damaged  fuel and distribution 
. theoretical analysis and experimental  verification  of 
vaporisation  rates for  radiologically  important  species 
containing for  example  plutonium,  higher actinides, 
caesium,  ruthenium. 
. radioactivity  distribution  in the  primary  circuit  during 
and following a  severe  core accident. 
1.B.2.5.Integrity of structure  under dynamic  loadings 
- Direct Action 
The investigation on  dynamic  material properties is strongly 
related  to the  study  of material properties  under  operational 
conditions : the  main objective is the  definition  of 
constitutive  laws for materials in  different  damage  situations 
and under dynamic  loading. 
Small specimens  of virgin  or damaged  materials  will be submit­
ted to tensile  tests at  different  strain  rates and 
temperatures. 
The special high load  dynamic  testing  machine  will be used for 
tests on large  specimens  (5000  mm2 cross section) to 
investigate  the influence of thickness, of  real size defects 
etc. and to  verify  the validity  of constitutive  laws. Tests 
using concrete  specimens  are also  envisaged. 
In parallel  to the  study  of material properties the extension 
and development  of dynamic  structure analysis  codes  will be 
continued. 
- Cost shared  action 
- Development  improvement  and validation of  codes  for design 
and analysis of  fast reactor structures (e.g.  primary 
containment,  reactor roof, piping  systems)  in presence  of 
dynamic  loadings. 
1.B.2.6.Outer containment  in accident conditions 
- Direct Action;  none proposed 

23 
- Shared Cost  Action 
This action  addresses  a number of  problem areas  which are 
related to the  definition  of a radioactivity  source  terra for 
the consequence  assessment  of a severe accident during  which 
sodium and possibly  fission  products  are released  into the 
outer containment. 
- Interaction  of sodium  with air,  water and concrete 
- Fission  product  transport  in the  secondary containment 
Modelling  of aerosol  behaviour 
- Outer containment behaviour 
Assessment  of outer containment with regard  to its  retention 
capabilities. 
I.B.3. Resources 
See table "Summary  and articulation  of action programme on the 
development  of nuclear  fission  energy". 
l.C. Implementation  of the  Council Resolution  of 22.7.1975 
concerning  the technological  problems  of nuclear  safety 
This action,  which is entirely  managed  from headquarters, 
started in 1976 by the  inscription  in the  budget of a line 
covering  the expenses  for staff (4A, 2B, 2C), The  objective  of 
this action  is mainly to perform comparison,  analysis  and 
synthesis  studies  in the  field of coordination  of research  and 
of harmonisation  of safety  methodologies, codes  and standards 
both for Light Water  Reactor  and Fast Breeder Reactor systems. 
In 1980 the Council agreed  upon a Commission  proposal  to add a 
contractual  part to this action,  in view of financially 
supporting  comparison,  analysis  and synthesis  studies  in the 
field of codes and standards  for Fast Breeder Reactors. 
The Commission  reports  periodically  to the  Council  the progress 
of this action.  The Commission  attaches  particular  importance  to 
this action  and proposed  that it should be continued during 
1984-1987  at the same  level of effort  than in the  past. 
1.C.1. Activities 
in the field of thermal  reactors  (LWR) 
- Studies  of technical  and regulatory  aspects 
. Information  exchange  on applied  safety  réglementation, 
criteria,  codes and standards with  the scope to reach a 
certain  degree  of harmonisation  by mutual  information 
. Identification  of general  and specific  safety  criteria, 

24 
codes and standards  and approaches  of specific  LWR safety 
problems  as they are applied  or under development  in the 
Member States. 
. Classification  and identification  of convergencies  and 
divergencies,  identification  of their causes,  proposals  for 
improvement . 
. Consultation  on national  réglementation  projects,  criteria, 
codes and standards  in the Member  States and on  projects  for 
codes and guides  prepared  in the  national context. 
. Coordination  of safety analysis  on specific  projects, coor­
dinated actions with other international organisations  in 
particular  with OECD/NEA and  IAEA. 
- Coordination  of national research  programmes 
. Handling  of information  on programmes  in general  which are 
provided  by national experts  and the JRC 
. Handling  of information  on detailed  programmes  Annual 
publication  of programme  sheets - Index of research  program­
mes 
. Exchange  of views and synthesis  on generic  problems 
. Identification  of themes for which cooperation  and a  concen­
tration of resources  is advantageous  and of  areas in which 
research should  be initiated. 
in the field of fast breeder  reactors 
- Comparison  of safety  measures  in view of drafting preliminary 
common safety  criteria  and guidelines 
- Information  exchange  and discussions  on current research pro­
grammes  performed  in the Member  States;  concertation  and 
coordination 
- Production  of state-of-the-art reports  in selected  areas and 
recommendation  for new  activities 
- Execution  of "benchmark"-type  studies  to compare  different 
approaches  applied  to the  treatment  of specific  problems. 
Codes and Standards  for Fast Reactors 
- Comparative  analysis  of national  standards  for manufacture, 
inspection  and quality control applicable  to Fast Reactor 
components 
- Comparative  analysis  of structural  codes such as elastoplastic 
benchmark  calculations, seismic  benchmark  calculations; design 
codes (such as ASME)  needed  for fast reactor  components  design 

25 
Comparative  analysis  of material properties  and speci­
fications  such as tensile  and stress rupture properties, 
allowable stresses,  creep  fatigue  data and data to assist 
material defect analysis. Materials  are considered  in function 
of their  suitability  for fast reactor  use. 
- Development  of safety  classification  guide for fast reactor 
mechanical  systems  and components  and comparison  with 
comparable  guides  outside  the Community. 
l.C.2. Resources 
The resources  necessary  for 1984-1987  amount to 2,2 MUCE for 
staff (A4, 2B, 2C) and 2 MUCE  for contractual  support  to 
comparison,  analysis  and synthesis studies  in the  field of codes 
and standards  for fast reactors. 
Total 4,2 MUCE (3,3 MUCE 1983  value) 
2. SUB-PROGRAMME  "NUCLEAR  FUELS AND ACTINIDE  RESEARCH" 
2.1. Objectives 
This sub-programme  is executed  at the  Transuranium  Institute  of 
JRC Karlsruhe.  It is  based on the  internationally establisbled 
experience  of this Institute  in the  field of nuclear fuels  and 
on its leading role  in the  field of actinide research. 
The sub-programme  has two  main orientations,  both directly 
relevant  for the  development  of the  nuclear  fission  industry  : 
- the improvement  of nuclear fuels  for fast breeder  reactors; 
- the safety of the  fuel cycle for  both light water and fast 
breeder  reactors. 
In addition,  and as the  focal point of a large cooperation  with 
scientific  laboratories  of the  Community,  a part of this sub-
programme  is dedicated  to the  investigation  of chemical  and 
physical  properties  of actinide  solids. 
In this way, a  basic knowledge  relevant  to all nuclear research 
is formed. 
The research  on nuclear fuels  for FBR,  covering  in the  past the 
largest  part of the  Institute's  activity,  is now  oriented 
towards  specification  of an optimized carbide  fuel. 

26 
The increasing  effort  concerned  with the safety  of the  fuel 
cycle, covers  a large part  of the sub-programme, and  provides 
support to other sub-programmes of the RAP  "Nuclear  Fission" 
(e.g., Reactor Safety  and Waste Management). It  covers a series 
of points  such as : 
- the determination  of the  thermodynamic  properties  at high and 
very high  temperatures  of selected nuclear materials,  which 
are relevant  for core accident analysis; 
- the study of the  oxide fuel under  transient conditions  to 
understand  fission  product migration within  and release  from 
the fuel; 
- the study of the  formation  of actinides  in pile (for  both LWR 
and FBR) relevant  for the  handling  of irradiated  and recycled 
fuel; 
- the study of powder and  aersol formation  in the  handling  of 
plutonium  fuels. 
The part  of the sub-programme  concerned  with actinide  fundamen­
tal research includes  work on  crystal  chemistry (preparation  and 
characterization  of samples)  and study of the  solid state 
physical  properties, directed  to establish  a general theory  of 
bonding  in solid actinides  as well as to  form a basis for a 
possible  application  of actinide containing  compounds as 
catalysts. 
2.2. Proposed  actions 
2.2.1. Operation  limits  of nuclear materials 
The project investigates  essential  aspects  of nuclear  mate­
rials : 
- the evaluation  of the  impact  of operating  and extreme  working 
conditions  on the  mechanical  and chemical  stability  of advan­
ced fuel for fast reactors 
- the determination  of the  thermophysical properties  of selected 
reactor  materials  at very high  temperature,  as needed  for core 
accident  analysis. 
Advanded  Fuel Optimization. 
Based on extensive information gained during research  programmes 
1977-80 and 1980-83 the  specification  of optimized  (as to 
burn-up,  rod power and  mechanical  stability)  advanced  fuel will 
be elaborated,  a carbide-rich  and oxygen-controlled  fuel for 
both helium  and sodium  bonding.  This development  will be follo­
wed and  supported  by the  elaboration  of a code describing  fuel 
behaviour  composed of  sub-models  tested  by suitable  experiments. 
The optimized  fuels  will be subjected  to fast flux irradiations 

27 
in order to confirm  the predicted  performance. 
Properties  of Reactor Materials  at Very High Temperatures 
Fast neutron reactor materials,  essentially  fuels and coolants, 
will be subjected  to high and very high  temperatures  and their 
thermodynamic  characteristics  will be determined.  In this 
context rapid expansion  upon heating  by laser pulse impact  will 
be one of the  methods  of investigation,  another  will be 
equilibrium  vapour  pressure  measurements  in a high temperature-
high pressure autoclave.  Measurements  of specific  heat at 
constant pressure  above the melting point  will  fill a gap in the 
knowledge  of thermophysical properties necessary  for the 
prediction  of material behaviour  under  accident conditions. 
2.2.2. Actinide Cycle Safety 
This project  aims at answering  questions  arising  from the impact 
of transuranium  elements  on the  safety of the  nuclear  fuel 
cycle : 
- measurements  of actinide formation  in-pile 
- analysis  of possible  mechanisms  of accidental release  of dust 
and aerosols  formed  during  fuel fabrication 
- demonstration  of the  potential  and limits of various reproces­
sing headend  methods  for advanced  Pu-fuels  and investigation 
of key reprocessing  problems. 
Formation  of Actinides  InPile  (FACT). 
The formation  of actinides  in high burn-up  LWR and FBR  fuel -
due to their radiation  hazards  - is a  decisive  factor for the 
handling  of irradiated  and recycled  fuel and for the  fuel cycle 
in general.  The formation  of heavy metal isotopes  and thus also 
minor actinides  (No, Am, Cm)  will be investigated with high pre­
cision under  typical  power  reactor  and prototype  FBR conditions. 
Computer  predictions  will be checked.  Radiation  dose will be 
calculated.  Capsule  irradiations  of mg amounts  as well as of 
fuel pellets  under  well-defined conditions  will be necessary.  In 
the latter  case isotopic  analysis  has to be  complemented  by 
chemical treatment  which  forms a natural  link to the  sub-project 
REPRO.  Finally  thermophysical  characteristics,  phase diagrams 
and fuel-clad  interaction  of fuel containing  significant  amounts 
of minor  actinides  like Np-237 and  Am-241  will be determined. 
Safe Handling  of Nuclear Fuels  (SHAPE). 
The handling  of nuclear  fuels,  essentially  Pu-fuels,  will be 
investigated  with special  regard  to dust and aerosol formation. 
In this context also production procedures  are reviewed  with 
regard to elimination  of dust formation  by the use of  gel-
supported precipated material  and optimal  homogenization  of 
mixed oxides  at low  temperatures. Equally, aerosols  formed  under 
accidental  conditions,  as in  glove box fires, will  be 
investigated.  Experimental  competence  required  in this field 

28 
forms the sound  basis of a  focal point for the studies of 
harmful  and poisonous  aerosols in the context of various 
industries  in the  Community. 
Fuel Reprocessing  (REPRO) 
Carbide head-end  reprocessing studies  will be completed  with 
investigation  of alternative processes. Key  problems  of nuclear 
fuel reprocessing  such das Pu-containing residues,  problems 
associated with  Np-237  and separation of actinides  from the 
reprocessing  stream  before  they enter the  waste  stream  will be 
treated. 
2.2.3. Actinide  Research 
This project  aims at investigating and  understanding  the 
chemical  bond in solid actinides with  emphasis  on intermetallic 
and simple binary  compounds  of the  least known  elements  in the 
first half of the series, especially Pa, Np, Am and Cm. 
Actinide  Chemistry 
Specific  compounds  of major  and minor  actinides are  produced  by 
suitable  crystal  growth  methods  with very high purity and 
reproducible physical and chemical  characteristics,  a necessary 
condition  not only for the sub-project "Actinide Physics" but 
also for the  combined  efforts  on actinide reserarch of the 
Member States of the  Community.  In addition,  their basic 
physico-chemical properties  like crystal  structure,  PVI-diagram 
and stability  regions  will be studied. 
Actinide  Physics 
The physical characteristics of well-specified actinide  com­
pounds representative of certain  bonding  types dare studied with 
special  consideration of surface properties. This is  done in the 
double context of studying the influence of 5f electrons on the 
chemical  bond and to  form a basis for possible  catalytic  appli­
cation of actinide  compounds. 
2.2.4. Transient  behaviour  of oxide fuels and  fission  product  
release  under severe  fuel damage  conditions 
Preparation of a  model  to describe the  behaviour  of oxide fuels 
in a transient of  power  or temperature.  Transient studied  will 
range from the relatively  mild devaiations  from normal  operation 
which dare inevitable as a  result  of fuel movements  or mismatch 
of coolant flow and  power  to the  extreme  situations of a  hypo­
thetical  accident in  which severe  fuel damage  can be  expected. 
Modelling and transient  experiments 
Basic theoretical studies  supported  by experimental  work on 
fission  product  migration within the  fuel lattice  will form the 

29 
basis for the model which  will be developed  and compared  with 
results from experiments  of more technological  nature.  These 
experiments  will include in-reactor transient tests  and 
simulation  experiments  using iradiated fuel  in the hot  cell. 
Fission product  release  under  accident conditions 
The severe  fuel damage  regime  will be covered  primarily  by 
examination  of fuel tested in the  course of reactor safety 
experiments.  Short  lives fission  product  release during  irradi­
ation experiments  simulating  severe  fuel damage  accidents  will 
be studied. 
Fuels used will include  FBR mixed oxide, LWR UO ^ and  possibly 
also LWR mixed oxide  varieties.  ^ 
2.3. RESOURCES 
Ref. to Activity  MUCE 
Activity  •.(1-98;3  values) 
2.2.1. Operation  limits 17.4 
of nuclear  mate­
rials 
2.2.2. Actinide cycle  .,:··;·'  .'. 28. 
safety 
2.2.3. Actinide research  13.8 
2.2.4. Transient  behaviour  of 6.5 
oxide fuels and fission 
product  release  under 
severe fuel damage  con­
ditions. 
TOTAL : 65.7 
3. SUB-PROGRAMME  "RADIOACTIVE  WASTE MANAGEMENT" 
3.1. Objectives 
Radioactive  Waste Management  has been successfully practised  in 
the Community  since several  decades  only as far as low  level 
wastes dare concerned.  Management  of wastes  containing long 
lived isotopes  (and  particularly  plutonium  contamined  wastes) 
and of ligh livel wastes  (that is wastes  arising  from reprocess-

30 
ing operations) has not yet  reached  the stage  of industrial 
maturity,  although  certain basic technologies are already  avail­
able. Last but not least the  definitive  storage  of these wastes 
is not yet practised. 
The broad  objective of RD  & D activities  of the  Community  is 
therefore to help creating a  comprehensive  waste management 
system,  capable  of assuring the safety of man and the protection 
of the environment. 
The twelve  year (1980-1992)  Community  action plan for radio­
active wastes,  approved  by the Council in 198C  (*) ensures  the 
necessary  concertation  within the  Community  as well as the 
orientation  and the continuity of the  activities. 
The objectives of  Community  action  will be : 
a) Concerning  the phases  treatment,  conditioning and handling 
of wastes  : 
- to improve  the existing  methods  of management  taking  advan­
tage of the technological  progress.  In particular, to  opti­
mize the management  methods  of low and  medium  level wastes 
and to put at the disposal of the  operators  more economi­
cal, more performing  and safer  methods. 
- to develop  and bring to maturity  treatment  and conditioning 
processes  for high  level wastes  and long  lived wastes,  when 
these processes  are not yet available. 
- to develop  processes  with similar  purpose  for those gaseous 
wastes which might  not in the future be  directly  rejected 
to the atmosphere. 
- to work out methods  of characterization,  criteria  of accep­
tance and guality control for  wastes  to be stored. 
b) Concering  the phase  of final storage  of high  level wastes  and 
long lived wastes 
- the demonstration  of feasibility  of final storage  in 
continental geological  formations  (salt,  granite, clay, 
etc) by the  study,  the construction and exploitation of 
experimental  vaults and the  installation  of underground 
prototypes. 
- the evaluation of  feasibility  of final storage  involving 
burial under ocean sediments  by laboratory and in  situ 
experiments. 
- the evaluation of safety of the different options of  final 
storage, by  developing  risk analysis  methodologies,  model-
(*) O.J. C  51/1 of 29.2.80. 

31 
ization of phenomena and  acquisition  of experimental 
results.  This approach  take? account  of the  iTnpossibT  litv 
to directly  demonstrate  safety  for very long periods  and is 
susceptible  of continuous  improvement  in the  light of 
experience  which  will be acquired  in experimental  installa­
tions . 
c) Concerning  management of  radioactive  wastes  as a whole 
- the optimization  of radioactive  waste management  with 
respect to safety and cost. 
- the integration  waste management  into a global strategy  for 
the fuel cycle  downstream the  reactor. 
- the study of the  plurinational  dimensions  of the  waste 
management and of  their influence  on management. 
To attain  these objectives,  it will be necessary  to continue 
without  hesitation  the effort  of Community R&D  both  within 
the Joint  Research  Centre  and through  shared  cost action 
which already covers, since  many years, a significant part  of 
the effort  in Member  States  (particularly  concerning  the 
final storage). 
Community  cooperation  and coordination  must be  reinforced 
according  to the  orientations  of the Community  action plan 
concerning  radioactive  wastes.  Also international cooperation 
in the broaded  sense must be  reinforced  as it is  only 
through  joint effort that  the solution  of the  problem  of 
final storage  will carry conviction with  the public. 
3.2. Proposed  actions 
The future actions  will be executed  within  the frame of plurian-
shared cost programmes and of  direct action  by the JRC in  strict 
cooperation.  The JRC  will contribute with  the results  of its own 
research, with its  scientific  support  and with its expertise. 
Other means of action could  be envisaged  in future in particular 
concerning  the study and realization  of pilot installations. 
The proposed  actions  are summarized  in what  follows.  It should 
be noted that they are defined  in some more detail  in the  case 
of the JRC programme,  which should  start in 1984. Conversely, 
the 3rd shared  cost action  programme  will start in 1985 (*),  and 
it is too  early to fix the details. 
3„2.1. Direct action 
Project 1. : Waste management and  fuel cycle. 
(*) The present  programme  covers  the period 1980-84  (O.J. N° L 
78/22 of 25.3.80). 

32 
This project  aims at improving future  installations  for the fuel 
cycle with a view of optimizing  the management  of wastes. 
- study of strategies  minimizing  the quantities  of alpha 
emitters  both from the point of view of feasibility  (experi­
mental  activities)  and of  interest  (cost/benefit  studies). 
In particular,  the potential  of the  process OXAL-MAW  will be 
studied on a larger  scale ; in 1980-82,  the application  of 
this process  to chemical separation  of the  actinides contained 
in the alpha contaminated  wastes  arising  from reprocessing 
plant had already  been studied.  Hot cells from the ADECO 
laboratory  of the  ESSOR complex  will be utilized.  This action 
will be strictly  coordinated with  the shared cost  action. 
- characterization  and control  of conditioned  waste from the 
physical  dand chemical point  of view. Non-destructive  methods 
of analysis  will continue  to be  improved.  Also new actions 
will be started  particularly  in the  field of physical charac­
terization.  Certain experiments could  be executed  in the ADECO 
hot cells.  This action  completes  and supports  an on-going cost 
shared action  (see subject 1 later on). 
Project 2. : Safety of waste storage  in continental geological 
formations, 
No substantial  reorientation  of the  high level waste  storage 
safety analysis  started  in 1974 by the JRC in  proposed.  Rather, 
the efforts  on risk evaluation  for alpha bearing  wastes  will be 
intensified.  These  latter  wastes  are not  included  in project 
PAGIS (Performance  Assessment  of Geological  Isolation  System) 
executed  in cooperation with  the cost sharing  action. 
The gathering  and validation  of the  necessary data  will be 
achieved  by laboratory long term experiments  on the  different 
barriers.  A collaboration  with CEN-SCK  Mol on the  study of 
plastic  clay formations  is existing  since 1980 and  will continue 
in view of the  importance  of connecting methodological studies 
to real experimental  sites. A contribution  of studies  on hard 
rocks as well as salt formations  will also be given, thus 
complementing  national laboratory studies. 
Coordination  with shared cost action  on project  MIRAGE 
(Migration  of radionuclides  in the  geosphere)  will also be 
contined. 
Project 3. : Feasibility  and safety of final storage  by burial 
under deep ocean sediments. 
This long term research requires cooperation  at World level in 
view of its multidisciplinary  and international  character. This 
cooperation  has already  started  under the aegis of ΝΕΑ, whose 
Working  Group "Sub-Seabed  Disposal"  is a reference point  in the 
subject. 

33 
The JRC  will concentrate on well defined options (for instance : 
burial by free  fall penetration) and on the  development  of 
specialized  equipment  (hyper  pressure laboratory for the  study 
of phenomena  of migration and of barrier  performance  under high 
pressure). 
In a following  phase,  the JRC  will endeavour  to stimulate the 
creation  of European  associations in the research  concerning  the 
problems  raised by possible  in-situ  experiments. 
Shared cost action  will continue to contribute to the 
feasibility  studies, in particular by engineering studies 
executed  by the specialized industries in the  Member  States. 
3.2.2. Shared  cost action 
The orientations given  here are preliminary.  They must be 
discussed with all  concerned  parties during  1983-84  : 
- preliminary studies to be  executed  in a coordinated fashion 
amongst  national laboratories in order to  complete  basic 
knowledge  (e.g. characterization of different  forms of 
wastes). 
- activities  aiming  at demonstrating  the validity  of certain 
processes  (e.g. waste  treatment)  or at validating certain 
options (e.g. storage in geological formations).  These  activi­
ties will be centered  around  pilot  installation  in Member 
States, if possible. 
- studies  concerning  the economy,  safety and regulatory  aspects 
of waste management  and, more generally, the strategies to be 
implemented  for each stream  of wastes. 
These studies and  activities  will require a large  exchange  of 
information and ideas on the  work of Member  States and an 
intense concertation at  Community  level. 
Subject 1. : Characterization and quality of conditioned  wastes. 
One activity,  which  has developed  in the  frame  of the  shared 
cost action since a  number  of years (programmes  1975-1979  and 
1980-1984)  links several laboratories in a close collaboration 
(concerted  programmes,  round robin tests, etc.) in the 
evaluation of the  performances  and of the long  term behaviour  of 
matrixes  for coating different  wastes  in view of their storage. 
This activity  will be continued  particularly  concerning  the 
control  of the quality of conditioned  wastes. 
The JRC  will contribute with its Project N° 1. 

34 
Subject 2. : Demonstration of treatment and conditioning 
processes in  view of an optimized  management  of 
wastes. 
This activity  will bring the  financial  support of the  Community 
to the development  of pilot scale of the processes already iden­
tified as the  most promising for an optimized  management  of the 
different  streams  of wastes, and  will ensure  the exchange  of 
information  and experience  amongst  the concerned organizations. 
All types of  wastes  will be considered, with  particular 
attention  being paid to alpha bearing wastes, to cladding 
wastes, and to  certain  wastes  of medium  and high  level of 
radioactivity  (e.g. residus of  dissolutio  in reprocessing 
operations). 
Subject 3. :  Long term migration of  radioactivity  in continental 
geological  storage. 
The evaluation of the  risk related  to final waste  storage in 
underground  installation  relies  on knowledge  about migration of 
radio-isotopes  from the conditioned  wastes  through  artificial 
barriers  (container,  filling  materials, etc.) and natural 
barriers  (the geological formation  itself  and its  overburden)  to 
the bisosphere and man. 
The proposed  action  will be based upon the continuation of 
Project MIRAGE  (Migration of Radionuclides in the  Geosphere), 
started  in 1983 with the JRC. It  aims at improving the  knowledge 
of migration  phenomena,  their importance and  their modelization. 
Subject 4. : Conception of  final storage of  wastes  in geological 
formation. 
The accent on  this project  will depend  upon the initiatives  of 
Member States in achieving experimental or  pilot  installations 
for geological storage. 
The work now in progress should, in any case, be  brought  to 
completion  (salt mine at Asse, experimental  clay vault at Mol, 
etc...). 
Subject 5. : Safety evaluation of  waste  final storage. 
An imported  effort  will be devoted to evaluate the safety of 
different  concepts of  final storage (both continental and  under 
sea bed). This  effort  will be based mainly on Project  PAGIS 
(Performance  Assessment  of Geological  Isolation  System).  Its 
first phase,  already  started  in 1982,  aims at gathering  existing 
information  and at choosing methodologies and scenarios. 
By 1986, an evaluation at  Community  level should  become 
available.  It would be the  resulterative  process of evaluation 

35 
already started at national  level since few years. 
This action  will be managed  jointly  with the JRC, and the 
radiation  protection  programme,  with participation of  Member 
States within the  frame  of point  2 of the Community  Action Plan 
concering radioactive  wastes. 
Subject 6. : Optimization of radioactive  wastes  management  ; 
strategy of  management  of different  waste streams  ; 
global strategy for the  fuel cycle downstream  the 
reactor. 
These studies aim at the optimization of  waste management  from 
the point of  view of safety and cost.  Experimental  support  will 
be provided as  necessary. 
The questions to be  examined  are : 
- Limitation in the  volume  and in the*  specific  activity  of the 
different  categories of  wastes  produced. 
- Quantitative appreciation of the different strategies with 
respect of  each waste stream  from source  to final disposal. 
- Global  management  strategy for the  fuel cycle downstream  the 
reactor ; different options ;  time schedule. 
- Plurational  dimensions  of management  ; influence  upon the op-
mi zation of  management. 
3.3. Resources 
The present  forecasts for the  programme  cost amount  to 46 M ECU 
for the Direct Action  (1984-87)  and 75 to 100 M ECU for the 
shared cost action  (1985-89).  The above  interval  is a 
consequence  of the necessity of preserving a large  degree^of 
flexibility  for the possible financing of experimental 
installations,  in particular for  the.final  storage of  radioacti­
ve wastes.  Such installations  should, in  principle,  be proposed 
for bilateral  or multilateral  cooperation within a  Community 
frame by the interested  Member  States. This is not yet the  case 
at the date of issue of  this document.  The Commission  has 
expressed  to the Council its interest to receive  such proposals 
and its  views about  the necessary  means. 
The amounts  corresponding  to the period  (1984-87)  of the plan of 
action are included in the following indicative table  which 
assumes  a 7 %  inflation  in the future years. 

36 
Objectives 
Direct Shared cost % of 
Action Action budget 
- Treatement,  conditioning, Project 1 Subjects  1 approx. 50% 
handling of wastes (in part) and 2 
- Final storage  of wastes Project 2 Subjects  3, approx. 35% 
underground 4 and 5 p.m. (3) 
under sea-bed Project 3 Subject 5 approx. 5 % 
(in part) 
- Optimization  of waste Project 1 Subject 6 approx. 10% 
management (in part) 
TOTAL BUDGET (1) 48.9 M ECU 40+3(2) + p.m. (3) 
(1) 1983 value. 
(2) For the  first 3 years of 3rd programme  and the  last year of 
2nd (present)  programme  (48 + 3 M  ECU in  actual values). 
(3) Pour mémoire.  (It concerns  the possible  participation  to the 
financing  of experimental  installations). 
4. SAFEGUARDS  AND FISSILE  MATERIAL  MANAGEMENT 
(Direct  Action  Only) 
4.1. Objectives 
The establishment  and the  upholding  of a credible  safeguards 
system for the nuclear materials  in circulation  in Europe is 
among the fundamental  elements,  which  condition  the acceptabili­
ty and the  development  of nuclear  energy  and is one of the  means 
to respond  to the  concern of the  proliferation risk  of nuclear 
weapons . 
Considering also  the importance  of the  economic  impact of a 
safeguards  system,  it is necessary  to establish  a European 
strategy  in this field for the 1990's and this involves  an 
important  Community  action and a concertation  with the national 
effort . 
The R and D  programme  proposed  by the JRC is  conceived  to 
provide technical  knowledge  to the  EURATOM  Safeguards  Directo­
rate and to the  European  plant operators  for the implementation 
of their  obligations  in the  frame of the  EURATOM  and Non Proli­
feration  Treaties  or other Agreements. 

37 
Particular  attention  will be paid to  find an equilibrium ir the 
programme  between  the technical  needs in respect to different 
safeguards  obligation and the  industrial  reality. 
For the execution of the  proposed  programme;  close collaboration 
will be maintained  with the national research establishment 
(directly  through  ESARDA)  dand with the  IAEA and US laboratories 
in the frame  of existing cooperation  agreements. 
The JRC,  which  gradually  developed  since 1969 its R and D 
programme  in the  field of safeguards,  has now the largest one in 
Europe.  It will continue,  through  multiple contacts, with the 
national  centres, the nuclear industry and the Inspectorates, to 
affirm its role as  focus  point for the R and D within the 
Community . 
4.2. Proposed  Action 
In order to  respond  to the objectives  mentioned  above,  the 
programme  has been subdivided into three projects. 
4.2.1. Methods  and instrumentation for nuclear material  assay  
and containment  and surveillance 
The objective of  this project is : 
- to develop  and to make available the  necessary  means  and 
methods  to establish and to regularly  verify  the performance 
in field  conditions of the  instruments  used for safeguards  and 
fissile  materials  management,  in particular for destructive 
assay (DA), non destructive  assay  (NDA) and  containment  and 
surveillance  (C/S). 
- to prepare  the necessary  conditions to  enable  the construction 
of reliable  instruments  suitable for routine use in  field 
(industrial  products). 
- to develop  new methods  or to adapt  existing  ones, for the 
assay of fissile  materials and  containment  and surveillance. 
The two major  activities  are : 
a) Evaluation of  performances  of nuclear material  assay  and con­
tainment  and surveillance  methods  and procedures  ; establis-
ment of validation and training laboratories. 
This subproject  aims at the establisment of perfcrniances 
values in  field for material  assay  and C/S instruments. 
The existing JRC laboratories or orther  specific  facilities 
such as the  spent  fuel or fresh  fissile  material storage 
facilities,  will be more adequately  equipped  for the  calibra­
tion of instrument  and methods  ; in particular for non 
destructive  assay and C/S. The laboratories, will.tieLmade. -

38 
avai to inspectors or  Member  State experts and  have to 
respo'I also to the increased request of  training.  Those 
1<: oora-ories  will create the conditions, which are close to 
those encountered in the  European  nuclear industry. 
b) Development  of methods  and instruments and  Industrialisation 
of Instruments and Devices. 
Some effort  will be dedicated to the  development  of new 
methods,  instruments or devices (such as seals) and data 
interpretational  models  needed  for particular  applications, 
where no satisfactory  solutions  have been obtained  until now 
and to prepare the  industrialisation  process with the 
European  industry for the reproduction of  series  of equipment 
originating  from the  development  at the JRC or  Member  States 
laboratories  and satisfactorily  tested in  field as prototypes 
by safeguards inspectors. 
4.2.2. Safeguards data ; rocessing, transmission and evaluation 
The objectives of  this project are : 
- to develop  statistical  and informatic  tools for the evaluation 
of nuclear material accountancy data provided by the operator; 
- to develop the necessary  tools (hard and software) for the 
evaluation  in field and at headquarters of  measurement  data 
taken by the inspector. 
Two subprojects  have been defined. 
a) Nuclear material accountancy data  management 
This sabproject  aims at the  creation  of plant category  speci­
fic rules and a data preparation  language  for the automatic 
insertion  of the  measurement  errors for the declared batches 
in lh>:. existing  statistical  material accountancy codes, in 
order to evaluate  different  material balance  characteristics. 
Furthermore a  critical  review  will be made on decision 
analy. i procedures for material accountancy in conncetion 
with the I3ADAM  (International  Safeguards  Data Management 
System)  code. 
b) Automatic processing, transmission and evaluation of 
inspection  data, produced by nuclear material assay and 
containment and  surveillance  instrumentation. 
The activities  in this subproject are the continuation of on 
going studies on the design and  development  of microprocessor 
interfaced  instruments and  related  software for in  field data 
evaluation  and subsequent  validation.  Furthermore, it is 
foreseen to design  detailed  evaluation procedures of  measure-

39 
ment data and instrument  performances. 
Finally,  a feasibility  study and a  demonstration  will be 
performed  on the on  line transmission  of inspectors  measure­
ments data into a local network  or directly  to headquearters. 
4.2.3. Integration  of safeguards  activités 
The objectives  of this project  are : 
- to analyse  the technical features  of proposed  safeguards  prac­
tices ; 
- to develop  mathematical  models  for describing  the safeguards 
relevant  parameters  of specific  parts of a  facility,  of a com­
plete facility  or of  parts of the  fuel cycle ; 
- to develop  a methodology  for the  design of some  specific  safe­
guards  activities  taking  into account  the operational 
constraints  from operators  and inspectors side. 
Four subprojects  have been defined  : 
a) Study of safeguards  practices 
This subproject  aims at evaluating  the adequacy  of the  per­
formances  of measurement  and C/S  procedures  for bulk handling 
facilities  in particular  for fuel fabrication  plants. 
Furthermore,  integrated  experiments  will be performed  to 
assess the quality  of several  accountancy  and verification 
activities  at the  input of reprocessing  facilities. 
b) Development  of a conversational simulator  for the  analysis 
and assessment  of safeguards  practices 
An upgraded  version  of an JRC  existing  plant simulator  for 
material flow  and measurement  systems  will be designed,  it 
will include also  C/S measures  and at a  later stage some 
statistical  decision analysis features. This simulation  tool 
will be designed  also for inspector  training  purposes. 
c) Application  of EXPERT  system  techniques  to safeguards 
studies 
The applicability  of and the  benefits  which may be  gained 
from EXPERT  system  techniques  to the  planning  of some 
specific  inspection  activities  such as physical inventory 
taking  will be studied. 
d) Analysis  of safeguards  procedures  through  the fuel cycle 
An analysis  will be made of the  shipper receiver difference 
(SRD) structure  for a number of  situations,  and of the 
material  balance  of large parts  of the  fuel cycle,  which pro-

40 
ceeds from the combination  of partial  balances  by material 
balance area  and SRD's. 
4.3. Resources 
The following  table summarizes  the distribution  of the  ressour-
ces damoung  the three different  projects.  The values mentioned 
should be considered  as indicative. 
Projects Total Ccst for 4 years 
(in MECUS) 
4.2.1. Methods  and instrumentations 30.8 
4.2.2. Safeguards data processing 6,1 
4.2.3. Integration  of safeguards 
activities 8,5 
TOTAL : 45 -4 MECUS 
5. SUB-PROGRAMME  "DECOMMISSIONING  OF NUCLEAR  INSTALLATIONS" 
(Shared cost  action  only) 
5.1. Objective 
Existing  experience  in the  decommissioning  of nuclear  installa-
lations is limited  (e.g.,  no large nuclear  power plant has yet 
been dismantled).  The aim of  Community  action in this field is 
the joint development  of a system of management  of nuclear 
installations  finally  shut down and of the  radioactive  wastes 
produced in their dismantling which,  at its various stages,  will 
ensure the safety and protection  of man and the  environment 
against the potential  hazards involved  in the  decommissioning  of 
these installations. 
In this context,  the proposed  sub-programme  pursues mainly  the 
following  objectives  : 
- To dispose  of efficient  surface decontamination techniques 
producing  little  secondary  waste ; a particular  objective with 
a view to substantially  reducing  the volume of radioactive 
waste is decontamination  to such a degree  that material 
treated can be  released without  restriction. 
- To dispose  of appropriate techniques  for the dismantling  of 
thick-walled  steel components  and reinforced  concrete 
structures,  and of the  auxiliary  techniques (e.g.,  remote 

41 
control),  required  to protect  the workers  against radiation. 
- To dispose of techniques  for conditioning  the special radioac­
tive waste materials  arising  from the dismantling  of nuclear 
installations  (i.e.,  steel,  concrete, graphite),  for final 
disposal . 
- To dispose  of more reliable  predictions  on the  consequences  of 
decommissioning  as to  radiation  exposures,  costs and waste 
repository  requirements  ; this involves optimization  of 
overall  decommissioning  schemes,  e.g.,  with regard  to the 
timing of dismantling  and to the mode of  waste disposal. 
- To dispose  of certain cost-effective  improvements for  the de­
sign of future  installations,  which  facilitate  their decommis­
sioning. 
- To provide guiding principles  for decommissioning. 
5.2. Proposed  actions 
5.2.1. Section  A of the  sub-programme  comprises seven  research 
and development  projects  relating  to the  following 
topics : 
1. Long-term  integrity  of building  and systems  ; 
2. Decontamination for decommissioning purposes  ; 
3. Dismantling  technques  ; 
4. Treatment  of specific  waste materials  : steel,  concrete  and 
graphite  ; 
5. Large containers  for radioactive  waste produced  in the 
dismantling  of nuclear  installations  ; 
6. Estimation  of the  quantities  of radioactive  waste arising 
from decommissioning  of nuclear  installations  in the Com­
munity ; 
7. Influence  of plant design features  on decommissioning. 
5.2.2. Section  B is concerned  with the identification  of 
guiding  principles,  namely  : 
- certain guiding principles  in the  design and operation 
of nuclear  installations  with a view to simplifying  their sub­
sequent decommissioning; 
- guiding principles  in the  decommissioning  of nuclear  instal­
lations  which  could form the initial  elements  of a Community 
policy in this field. 
5.2.3. Section  C is mainly concerned  with the testing  of new 
techniques  within the framework  of large-scale  decommissioning 
operations  undertaken  in Member  States. Besides,  the exchange  of 
information  on such operation  would be promoted, for  example  by 
delegating experts  from other Member  States. 

42 
This proposed  sub-programme  takes up the  themes  of the current 
programme  (1979-1983)  on the  decommissioning  of nuclear  power 
plants,  but includes section C as a new item. It  would again be 
implemented  by the way of  shared-expense  action,  which proved  to 
be especially suited for  this fiels of research. 
5.3. Resource 
The following table gives a  break-down  of the resources of the 
sub-programme  and their planned  utilization  (in million  ECU, 
over the five years 1984-1988): 
Item Community  budget 
Section A 5.5 
Section B 0.2 Section C 4.0 Staff and Administration 2.4 
TOTAL 12.1 
XXX 
The Council is  invited  to note the orientations contained in 
this document  in view of the discussions on the  Commission 
proposals for the JRC  programme  (nuclear section),for a  shared 
cost action in the  field of "Safety of Fission Reactors" and for 
a shared  cost action in the  field of "Decommissioning  of Nuclear 
Installations". 

SUMMARY  AND ARTICULATION  OP ACTION  PROGRAMME ON THE  DEVELOPMENT  OF NUCLEAR  FISSION  ENERGY 
(All cost figures are preliminary and  indicative.) 
I Reference Direct action Shared cost Action 
Sub programme 1 Safety of Fission Reactors to Activity MUCE MUCE Remarks 
• -Activities 1983 values 1983 values actual values 
1.A LWR Safety l.A.2.1. &eliability  and risk 16.7 1.9 
J Evaluation 
i 1 • .A. 2.2. Human factors and Man- ~ 3.9 
i 
j machine Interaction 
1.A.2.3. Integrity of compon­ 19.6 5.2 
i ents and Systems 
1.A.2.4. Investigations  of core 43.1 3.9 
and cooling system cif 
normal behaviour 
(< 1200°C) 
1.A.2.5. Reactor core and 13.4 12.0 
cooling system under 
severe accidc;nt con­
ditions (> 1200°C) 
1.A.2.6. Reactor outer - 14.3 
containment phenomena 
during severe accident 
conditions • 
1.A.2.7. Dispersion of fission - 7.1 
products in the atmos­
phere . 
l.B. LMFBR Safety l.B.2.1. Instrumentation,  Con­ - 3,2 
trol and Protection 
1-B.2.2. Integrity of components 10 7.2 
and structures 1 
I 1.B.2.3. Reactor core and 10 1 bA 
cooling systems in off-
i _ i norm --1 conditions 

Sub programme  1 Safety of Fission Reactors Reference 
to 
Activities Activity Direct :action 
MUCE 
1983 values Shared cost Action 
MUCE 
1983 values actual values Remarks 
l.B.2.4. 
1.B.2.5. Severe accident 
analysis 
Integrity of struc­
tures under dynamic 
loadings 63.9 
15.5 11.3 
1.4 
l.B.2.6. Outer containment 
in accident condi­
tions 3.2 
Sub-Total 
192.2 Sub-Total 
68 Sub-Total 
81.3 
I.e. Implementation  of l.C.l.  LWR &  LMFBR - 3.3 4.2 
Council Resolution  of coordination  of 
22.7.75  concerning  the safety  Research, 
technological  problems  Studies  on metho-
of Nuclear Safety dologies,  codes 
and standards 
TOTAL 192.2 71.3 85.5 

Sub programme 2  Nuclear  fuels and Actinide 
Research Reference 
to 
Activities Activity Direct action 
MUCE 
1983 values Shared c 
M 
1983 values ost Action 
UCE 
actual values Remarks 
Sub programme  3 Radioactive  Waste 
Management 2.2.1. 
2.2.2. 
2.2.3. 
2.2.4. Operator  limits  on 
nuclear materials 
Actinide  research 
safety 
Actinide  research 
Transient Behaviour 17.4 
28 
13.8 
6.5 
TOTAL 65.7 -
3.1.A. 
3.1.B Treatment,  condi-
tionning  and 
handling 
Final storage 
(underground) 
Final storage 
(under seabed) 19.6 
21.5 
5.0 25.5 
17.8 
+ pm 
2.5 
3.l.C. Optimization 2.8 5.2 
of management 
TOTAL 48.9 43 
+ pm 51 
+ pm 

Sub programma 4 Safeguards  and fissile 
material  management Reference 
to 
Activities Activity Direct action 
MUCE 
1983 values Shared cc 
1983 values >st Action 
IUCE 
actual values Remarks 
S 1 fi 
4.2.1. Methods  and 30.8 -
Instrumentation 
4.2.2. Safeguards  Data pro­
cessing,  transmission 
and evaluation 6.1 
4.2.3. Integration  of 
safeguards  activities 8.5 -
Sub programme 5 Decommissioning  of 
Nuclear  Installations Sub programme 5 Decommissioning  of 
Nuclear  Installations TOTAL 45.4 -
Sub programme 5 Decommissioning  of 
Nuclear  Installations 
J5.2.1. R&D Projects - 6.2 
5.2.2. Guiding  principles - 0.2 
5.2.3. Testing of new 
techniques 4.6 
TOTAL 11 + 12 

CONTRIBUTION  OF THE RESEARCH  ACTION PROGRAMME  ON THE DEVELOPMENT  01' NUCLEAR  FISSION  ENERGY  (1984-1987)  TO 
THE OBJECTIVES OF THE  SCIENTIFIC  AND TECHNICAL  FRAME-WORK  PROGRAMME  1984-1987 
! - • Objective 4. Improving  the Mana- Objective 6. Improving  living and working conditions 
J gement of energy resources. TOTAL Scientific  and technical  Objec­
tive 4.1. Developing  nuclear 
fission energy (In  particular 
its safety aspects). Scientific  and technical Scientific  and technical TOTAL Scientific  and technical  Objec­
tive 4.1. Developing  nuclear 
fission energy (In  particular 
its safety aspects). Objective  6.1. Improving Objective  6.2. Protecting Scientific  and technical  Objec­
tive 4.1. Developing  nuclear 
fission energy (In  particular 
its safety aspects). safety and protecting 
health. the environment  and prevent­
ing pollution. 
Sub-Programme 1. 
Safety of fission Reactors 74 % 195.5 MECU 13 % 34 MECU 13 % 34 MECU 263 .5 MECU 
Sub-programme 2. 
Nuclear fuels and Acti­ 100 % 65.7 MECU 65 .7 MECU 
nide Research 
j 'sub-programme 3. 
Radioactive  Wastes Mana­ 70 % 63.9 MECU 15 % 14 MECU 15 % 14 MECU 91 .9 MECU 
gement . 
Sub-programme 4. 
!?•-( F'eauards and fissile 100 % 45.4 MECU 45 .4 MECU 
ials management 
|Sub-programme 5. 
becommissing  of 100 % 11 MECU 11 MECU 
inr installations 
1OTAL 
i -381.5 MECU 48 MECU 48 MECU 477. 5 MECU 
! 
NOTES : 
1. till figures  are approximate  and expressed  in 1983  values. 
2. A notain^i  contribution  to the  objective  "promoting  industrial  competitiveness" 
must be  attributed  to sub-programme 1  "Safety of fission  reactors". 

Opinion  of the  Euratom  Scientific  and Technical 
Committee  on the  Commission's  proposals on the 
1984-1987  programme  of the Joint Research Centre 
(nuclear  part), and on the  1984-1987  programme 
of shared-cost action on reactor safety 
The Scientific  and Technical  Committee,  at the  meeting  of 20 May 
1983, examined  the communications  to be submitted to the Council by 
the Commission  on the  above mentioned  programme. 
The Committee  had already discussed, at its previous  meeting  of 
18 April 1983, the  Commission  proposals concerning the  framework 
programme  of research,  development  and demonstration of the  scientific 
and technical  activities  of the  Communities  for the period  1984-1987 
(doc. C0MC82)  865 final).  At the  same meeting  the Committee  had 
discussed the guidelines of the proposed actions in the  field of the 
development  of nuclear  fission  energy as described in  document  XII/316/ 
83 "Proposal for a  1984-87  action  programme  on the  development  of 
nuclear  fission  energy". 
At the meeting  of 20 May 1983 the  Committee  discussed the JRC 
programme  and the shared-cost action on reactor safety in the  light of 
the Commission's  proposed action  programme  for 1984-87  on development 
of nuclear  fission  energy. The  Committee  welcomed  this overall insight 
into Community  R, D and D  activities  in the  field of nuclear  fission 
energy. 
Specifically,  the Committee  addressed  itself  to the nuclear safety 
programme  which is the subject of both  direct  action and shared-cost 
action and also to the actions  which are the nuclear part of the proposed 
JRC programme  only. 

General  considerations 
1. The Committee  stressed to the  Commission  the need to retain  flexibility 
in the formulation and execution of the  programme.  However,  the Com­
mittee took note of the  fact that it  would not be possible to finance 
a major  new initiative  such as the construction of a large scale 
machine  from present  resources and that  such initiative  would  require 
fresh budgetary  provision. The  flexibility  currently available  would 
suffice  to fund new projects of the order of 10-15 MUC only. 
2. In order to  enhance  flexibility  the Committee  stresses the  need to 
have clear  lines of managerial  responsibility. 
3. The Committee  recognizes that  programmes  of this scale are evolution­
ary in nature  and the  recommendation  which  follow  seek to advice the 
Commission  in the  light  of this consideration. 
4. The Committee  wished  to be associated with and involved in  this 
evolutionary  process  and it  particularly  asks to be supplied with  such 
information as  will give it a  full historical  picture. 
5. The Committee  notes  with pleasure the increased provision for  shared-
cost actions in the  present  programme,  recognizing the  multiplier 
effect which  operates  on such actions. 
II. Recommendations 
Subject to the  comments  listed  below,  the Committee  approves  the 
general  direction  of the  programme  and the  apportionment  of resources. 
II. 1. FUSION 
The Committee  noted  that in the current cost-shared action  programme 
in fusion a  total of about  45 MUC  will be devoted  by the  Commission 
to technology  activities. 

The Committee  endorses  the need for research into fusion safety but 
considers that now and for  some considerable  time to come the work 
should be  focused  on generic issues. 
It considers that  this work should include  some consideration of 
the management  of fusion  waste. 
11.2. REACTOR  SAFETY 
The Committee  supported  the expected  close  liaison  between  shared-
cost and direct actions and  drew attention to the  importance  of 
appropriate  Community  participation in  extra-Community  projects. 
The Committee  suggested  that within the evolution of the  programme 
an effort  should be  made to transfer resources to the  area of 
accident prevention (e.g.  human  factors,  man/machine  interface, 
maintenance  of components  and systems)  from the area of accident 
mitigation.  However,  the problem  of fission  product  deposition and 
decontamination  should be analysed at  Community  level.  The potential 
use of the large  containment  volumes  available at JRC for H^  distribu­
tion and combustion  studies should be investigated. The  Importance  of 
strengthening the  LOBI project and the  full exploitation of the 
experimental rig has  been emphasized. 
The Committee  stressed the  importance  of LMFBR  safety and  agreed  on 
the general outline of the  corresponding  programme. 
11.3. RADIOACTIVE  WASTE 
The STC stresses the  importance  of all  activities  related to alpha-
waste management  and aiming  both at diminishing the alpha  content  in 
waste and at  fully characterizing it in  view of its disposal. 

II.4 CONTROL  OF FISSILE  MATERIAL 
The Committee welcomed the  proposed increase  in this area and 
particularly  endorsed  the proposals  to set up a  calibration  laboratory 
and to provide  training  facilities  for safeguards inspectors  and plant 
operators . 
II.5. NUCLEAR  FUELS AND ACTINIDE  RESEARCH 
The Committee  notes and approves  the intention  of the Commission to use 
part of the  potential  of the  Karlsruhe establishment  for the  benefit 
of the programmes  II 2, II 3 and II  4. 
The Committee  recommends  the Commission to  reconsider  the ressources 
devoted to the  study of advanced  fuels and to the  safe-handling  of 
fuel elements. 
III. FINAL REMARKS 
The above are a few  brief comments  which were made during  a course  of 
an overshort  discussion  and the Committee  will wish to return  to the 
individual  programmes  in much more detail  before  their implementation  is 
finally  initiated. 

FINAL ADVICE 
REACTOU SAFETY  SECTION  OF THE 1984-87  RESEARCH  ACTION PROGRAMME 
29th ACMP-Reactor  Safety,  16-17 May 1983 
The 29th meeting  of the ACMP-Reactor  Safety took place  on 16-17 May 
1983. Its  primary task  was to  discuss  and give advice  on the  general 
objectives  of the  Reactor Safety  Programme  as they are proposed  in the 
Commission  documents  (parts  of ACS-335-e  "Proposal  for a '984-87 
Action Programme  on the Development of  Nuclear  Fission  Energy", ACS-
336-e "The  Future  Activities  of the .JRC",  relevant  to Reactor Safety, 
ACS--332-e  "Proposal  for a Shared-Cost  Research  Programme  on Reactor 
Safety 1984-87" and  ACS-33'!-e  "Proposal  for the JRC 1984-87  Multiannual 
Programme"). 
The ACMP was informed  at the  beginning  of the  meeting  that the pro­
posals had been  prepared  following  the strategy  outlined  in document 
C0P-i(82)865-final.  This strategy mainly foresees that all  Commission 
sponsored research  activities  should  satisfy  the objectives  outlined 
in the framework  programme  and should executed  by either  direct 
(JRC) or shared-cost actions  or a combination  of these. 
The Committee  recognizes  the value of the  proposals  of the Commission 
which is exoected  to increase  the overall  benefit  and to  favour the 
integration  of Communitary  research  activities.  The ACMP supports 
the expected close  liaison  between the  proposed  shared-cost actions 
and the direct  actions  for the  various  themes of the programme. 
There was general  agreement on the Commission  choices  of the themes to 
be pursued  and six  delegations  gave support  to the  general balance 
between the  direct  actions  (JRC) and  shared-cost actions while  empha­
sizing that a further examination  of detail  would be  required.  The 
Dutch delegation requires further information  and more consultation 
before taking  a position.  The German  delegation  wanted to  place more 
emphasis  on achieving cooperation  among member  countries through con­
certed .ction  in addition  to shared-cost action  and also wanted to 
maintain  a reservation  obout the budget of the  shared-cost action  and 
balance between  this action  and the  direct  action  programme. The 
French delegation  gave a  qualified  approval  in which, if a modification 
in the shared-cost  budget is  requested,  this modification should  be 
made on the  basis of priorities  related  to the  activities  for which 
JRC competences may  increase  the value of Community  collaboration. 
The programme  discussion  was divided  into four main headings,  i.e. 
Accident Prevention  and Accident Analysis  for LWRs and LMFBRs 
respect  ively. 

Concerning Accident Prevention in  Light Water Reactors, the  Committee 
agreed on the proposed  work in the areas of Risk and  Reliability  Assess­
ment as well as Integrity  of Components  and Systems.  Some delegations 
were in favour of a  more direct  involvement of the JRC in the area of 
Human Factors. Others  stressed  the importance of strengthening the 
Commission  effort  in the  development  of PRA methodologies. The 
Committee  took note that the  Commission  has started  a study on the 
feasibility,  value and  possible  programme  for a medium  size vibrating 
table for seismic research. It was emphasized that the JRC should 
collect  data on  similar  installations  and related  research  programmes, 
including  those outside the  Community,  as a part of  this study. 
Concerning Accident  Analysis  in Light Water  Reactors, the  Commission 
presentations  divided  the field into the three regions, for con­
venience: 
- core phenomena  not exceeding  1200°C 
- core phenomena  exceeding  1200°C 
- outer containment and  fission  product behaviour in severe accident 
conditions. 
1) There  is a general wish to  maximize  the benefits  of LOBI for the 
Community  and there is support for the proposed  staff  increase. 
The associated  activity  of code assessment is supported and a  need 
to well coordinate  this activity  with other group  activities  con­
cerned with  codes (CSNI)  was emphasized. The  need to properly 
integrate  into the international  framework  of activities,  including 
in particular  the activities  in the  member  countries (e.g.  BETHSY), 
was underlined. To  this end, a combination of the  different  con­
sultative  groups (LOBI,  Group A) tends to be supported. 
2) The proposed JRC  programme  of severe accident  analysis  explicitly 
integrated  with the proposed shared-cost  actions  was generally 
considered  a desirable  way to evolve towards a  Community  view of 
the LWR severe accident  phenomenology.  However,  a possible  con­
flict between  personnel requirement for  this action  and the  code 
assessment  under  1) above  was recognized. The  Committee 
wishes to rebalance the  staff between  these two  programme 
areas with the  intention  of reinforcing  code assessment  work on 
thermohydraulic  aspects. 
3) The shared-cost  action  on external  gas cloud explosions should 
continue  to the necessary completion of the on-going  work. 
It is considered appropriate to begin the  first shared-cost  action 
in the two important areas, hydrogen  phenomena  and fission  product 
behaviour in the containment. 
In view of the launching of the shared-cost  action  on hydrogen 
phenomena  and fission  product behaviour in the containment, the JRC 
should acquire, at  modest  level  initially,  a competence  in these 
two areas. 
The theme  of atmospheric  dispersion  of fission  products is a 
particularly  suitable  area for  Community  collaboration. 

Concerning  Accident Prevention for  LMFBRs  the Committee  agrees 
generally on  shared-cost  activities  in the  field  of instrumentation 
control  and protection.  There  should be a contribution to  these 
studies  from the JRC. The  Committee,  while generally supporting 
the integrity  of components  and structures  activities  suggested  that 
these should be concentrated on the  development  of generally 
applicable  models. 
The Committee  approved  the overall objectives of the  work proposed 
under the heading  Accident Analysis for  LMFBRs. 
It realized that the  work on sodium  boiling  performed  by JRC  needs 
reorientation  by the end of 1984 and that the  Committee  will have to 
give eventually  recommendations  on such reorientation. 
The Committee  took note that the  in-pile  experiments  on fuel 
behaviour  are in the planning  phase  and that only a few tests are 
included in the  proposed  budget. 
In the area of Severe  Accident Analysis the  Committee  places  priority 
on the  utilization  of existing  installations  and agreed  that before 
starting  new activities,  the existing  programme  should be properly 
concluded.  Strong  support  was given for the  work on integrity  of 
structures  under dynamic  loading. Calculational tools  developed  or 
under development  should be  maintained.