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COM (83) 398 
 
 
Vol. 1983/0 149 
  
 
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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, 
p. 1), tel que modifié par le règlement (CE, Euratom) n° 1700/2003 du 22 septembre 2003 
(JO L 243 du 27.9.2003, p. 1), ce dossier est ouvert au public. Le cas échéant, les documents 
classifiés présents dans ce dossier ont été déclassifiés conformément à l'article 5 dudit 
règlem ent. 
In accordance with Council Regulation (EEC, Euratom) No 354/83 of 1 February 1983 
concerning the openin g to the public of the historical archives of the European Econom ic 
Communit y and the European Atom ic 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, 
27.9.2003, p. 1), this fi le is open to the public. Where necessary, classified documents in this 
file have been declassified in conformity with Article 5 of the aforementioned regulation.  
In Übereinstimmung mit der Verordnung (EWG, Euratom) Nr. 354/83 des Rates vom  1. 
Februar 1983  über die Freigabe der historischen Archive der Europäischen  
Wirtschaftsgemeinschaft und der Europäischen Atomgem einschaft (ABI. L 43 vom  15.2.1983,  
S. 1), geändert durch die Verordnung (EG, Euratom) Nr. 1700/2003 vom 22. Septem ber 2003  
(ABI. L 243 vom 27. 9.2003, S. 1), ist diese Datei der Öffentlichkeit zugänglich. Soweit  
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der genannten Verordnung freigegeben.  
COMMISSION  OF THE  EUROPEAN  COMMUNITIES 
COM(83)  398 final. 
Brussel,  21 June  1983. 
PROJECTS  OF EUROPEAN  SIGNIFICANCE 
(Interim  Report from  the Commission  to the  Council) 
COM(83)  398 final. 

Commission  of the  European  Communities 
Joint Research Centre 
PROJECTS  OF EUROPEAN  SIGNIFICANCE 
Introduction 
Three preliminary studies  were begun in March 1983 following  the Council 
meeting of the 10th of  that month in which the Commission  was requested  to 
study projects  suitable  for siting at the JRC  Ispra Establishment. 
Terms of reference included examination  of : 
- opportunity  and need at Community  level; 
- feasibility  at Ispra; 
- investment costs. 
The subjects  examined  are : 
- a Tritium  Handling Laboratory; 
- a Vibrating  Table; 
- Ignitor. 
These subjects being  of differing  natures,  different  elements  have had to 
be taken  into account  in each case and the  rate of progress  has not  been 
uniform.  As a  result,  it is not yet  possible  to come to any  definite 
conclusion  and statements  must be regarded  as being very preliminary 
observations  to be  confirmed  as the  studies progress. 
1. Tritium  Handling Laboratory 
The need for a  central  European  laboratory  was particularly  stressed  by 
the Fusion  Review  Panel held  in 1981, to  serve the fusion  reactor 
research  programme.  The facility,  which would be placed at the  disposal 
of all the fusion associations,  would be multipurpose  and be  able 
to handle some 50 to 100  grams of Tritium. 
Advantage  could be taken of the  existing  protected area  around  the ESSOR 
installation  which is already  licensed  to handle  radioactive  materials 
and has an 80  metres  high ventillation  stack.  The reuse of existing 
building  to house the laboratory  is being evaluated. Investments  would 
be expected  to be of the  order of 10 MioECUs  (1983-value). 

2.-
2. Vibrating  Table 
Vibrating  tables  are fairly  widely  used to investigate  the behaviour  of 
structures  under dynamic  loading conditions. Installations  in Member 
Countries  range  from 0,5 to 25  square  metres  area with static  load 
capacities  up to 25  ^onnes. 
A table of some 40 m (6 m x 6 m) and 100  tonnes  capacity  would  represent 
an important  step forward  in the  testing  of structures  under  realistic 
conditions  and could thus be considered  to be an  important  and significant 
European  facility. 
The installation  of a table of this size at Ispra would not be  expected 
to present  problems  concerning  space,  geological conditions  or power 
supply. Since  the evaluation  of need in various applicational  fields is 
still at an  early stage the optimal characteristics  of the  plant are far 
from being established  and a  wide range of possibilities  still  exists;  it 
follows that  no real cost analysis  can yet be made.  However,  it might be 
reasonably  assumed  that the investment  for the  machines  outlined  above 
would fall between  50 and 200  MioECUs. 
3. Ignitor 
No attempt  has been made in the  study to assess the need for such a 
machine.  Indeed,  it is  accepted  that such an opinion  would  properly  come 
from the Fusion Associations  and for the moment no  such proposal  is 
before them for consideration  under the Fusion Programme. 
The possibility,  and the  advantages  of siting an Ignitor project  at Ispra 
are analysed  in the  study,  should  such a project  be proposed  by a fusion 
association,  and adopted.  The results yielded  so far  seen to suggest 
siting at Ispra to be  both feasible  and advantageous. 
Enclosed  are the  three interim reports  submitted  to the  attention 
of the JRC  Governing  Board on June 14th, 1983. 

1. TRITIUM  HANDLING LABORATORY 
1. 1 The need of a European tritium laboratory (ETL) 
Tritium  problems are of paramount importance in the design and 
operation of fusion reactors and machines of the next generations. 
One of the key issues of the commercial fusion power reactors 
will  be that  of breeding the tritium  which  is consumed during 
operation, to recover it and refuel without the need of extra mural 
reprocessing. In the experimental reactors  (NET/lNTOR)  possibly-
only  a fraction of the burnt tritium  will  be compensated by the 
reactor production, the remaining  part  being supplied from out­
side.  However such machines  will  be confronted  with  all the as­
pects  of the tritium  cycle,  namely: 
. plasma heating and  fuelling; 
. plasma exhaust reprocessing; 
. tritium recovery from blanket; 
. coolant detritiation; 
gaseous  wastes  and ventilation processing; 
. handling of tritiated components from reactor and subassemblies. 
Tritium  has been  utilized  for many years already in the countries 
of the European Community in the  field  of  biological,  biochemical 
and chemical research and even for industrial and commercial 
applications.  The confinement and conditioning of tritiated waste 
waters arising in nuclear  fuel  reprocessing have also been objectives 
of research efforts in the Community. 
Tritium  is produced in macroquantities in classified installations of 
the two nuclear weapon  states  France and Great  Britain.  These two GB (83) 30 

countries have declared, in a  statement  at the  Atomic  Questions 
Group  in December 1981, to be disposed to the release of know-
how in tritium technology relevant to fusion. However it i s now 
recognized  that,  although the know-how acquired in the military 
applications  willle  very useful to tackle the fusion reactor pro­
blems, the operational conditions  typical  of fusion for energy 
production  require a complementary and specific effort on  tri­
tium  problems in the next years in Europe. This point was  stres­
sed, among others, by the Fusion Review Panel held in 1981 and 
is confirmed by the fact  that  European Fusion Technology Pro­
gramme 1982-1986  will  include activities on tritium. The Fusion 
Review  Panel sipported the need of a central tritium laboratory in 
Europe mainly to demonstrate, in relation to licensing procedures, 
the safety of the tritium manipulation techniques for peaceful 
applications of fusion. It has to be noted  that,  also in USA and 
Japan,the  need of constructing a tritium laboratory devoted to 
fusion  problems has been recognized. The  American  facility  (TSTA) 
is ready for operation in Los Alamos whereas the  Japanese  one is 
under construction at  JAERI. 
In the last few years, the  assessments  carried out in the frame of 
the NET/lNTOR  project to evaluate the  fuel  cycle processes, have 
made clear the necessity of disposing also in Europe of a labora­
tory where the components related to  these  processes can be  tested 
in conditions  similar  to those  of fusion power reactor in order to 
optimize  their performance. This laboratory must be  flexible 
enough to accommodate alternative components and systems as 
they  will  be proposed and developed in Europe in the frame of the 
fusion  technology activity. The free accessibility of the laboratory 
to the European research staff and industry  represents  a very im-

portant aspect to ensure the usefulness of it.  JRC-Ispra  appears 
adapted to host and  operate  such a laboratory for the  following 
reas  ons : 
. it has achieved experience on  fusion  technology problems 
and,  in particular, on those re lated to the  NET/lNTOR  con­
ceptual  design; 
. it is largely devoted to nuclear safety problems; 
. it is capable to host the European  teams  which  will  have to work 
at the  facility,  even for  long  periods (European school and other 
facilities). 
1. 2  Overview  on activities on  tritium  technology in the  
European  Community 
At the KFA  Jülich  the problem has been approached of separating 
hydrogen  (and tritium)  from  gas  streams  (by catalytic devices) 
and of  limiting  tritium  permeation by protective layers in  heat 
exchangers of  HTGR  cooling  systems.  Both  KFA  Jülich  and KFK 
Karlsruhe  have examined various techniques of  tritium  enrichment 
in waste waters. At the Max  Planck  Institute for Plasma Physics 
at Garching,  experimental studies have been performed speci­
fically  in relation to the  fusion  technology concerning the prepara­
tive  separation of the hydrogen isotopes by gas chromatography 
and the clean-up of atmospheres of (secondary) containment sys­
tems. 
The  CEN  Mol  has been  actively  involved  in the  field  of  tritium  re­
covery  from  waste  streams  arising in nuclear (fission)  fuel  repro­
cessing. 
All the above mentioned activities have been performed either on 
the basis of simulation  with  hydrogen and/or deuterium or, at the 
most,at tracer levels of  tritium.  At both the  Garching  and the  Mol 
centres,  pilot  installations are being prepared for the experimen­
tation  of the processes  with  more representative levels of  tritium 
(up to  1000  Ci). 

TABLE  1 - European  fusion  technology  programme  1982-1986 
First round accepted contracts on  tritium 
Task  Country Accepted Time Technical 
ceiling  MECU schedule description 
T.1 D 1.10 82 - 84 fuel clean-up 
F 0.37 83-84 system 
1.2 F 1.20 83-86 tritium  recovery 
T.3 
T.4 
T.5 
T.6 UK 
B, F, UK 
D 
F 
D 
F 0.15 
1.5 (max) 
1.70 
1.60 
2.85 83- 85 
83- 86 
83-86 
83-86 
83 - 86 
83-86 from waste streams 
tritium  detector 
electrolytic cell 
air decontamination 
system 
industrial development 
of large components 
TABLE  2 - Research  contracts  on tritium  bearing  waste  from  reprocessing 
Programme Contractor  CEC  contribution Title 
period  KECU 
75/79 CEN Mo! 371 
80/82 CEN Mol 393 
83/84 CEN Mol 291 
75/79 KFK Karlsruhe 83 
TU Karlsruhe 
75/79  USAEA  Harwell 25 
75/79  UKAEA  Harwell 30 
80/84 KFK Karlsruhe 58 Separation  of T from aqu. effluents 
Separation  of T from aqu. effluents 
Separation  of T from aqu. effluents 
T-enrichment .. on hydrophobic catal. 
T immobilisation 
T immobilisation by incorporation in 
inorganic solids 
Characterisation of conditioned cladding 
material (T release) 

CEA  and  UKAEA  have conceived, in the frame of a contract 
with  JET, a tritium handling system,  specifically  taylor-made 
for the  (rather  limited) requirements of this installation. In 
the frame of the  INTOR  workshop,France has contributed in the 
conceptual studies of the main tritium systems, namely the  spent 
plasma reprocessing  line,  the blanket processing  line,  the waste 
processing lines, and the neutral beam  line. 
Among  the non-classified experiences it must be mentioned the 
recovery of tritium from heavy water at the Von Laue-Langevin 
Institute at Grenoble  with  a yearly through-put of up to 10^ Ci. 
Part of the basic studies on physico-chemical  parameters  of 
materials (e. g. permeation) performed in the French military 
programme hasbeen published (Montrouge). 
In UK,Harwell  is claiming  to dispose of relevant experience in 
(tritium)  radiation damage on materials. 
On the Commission's  level,  Table 1 gives an overview on the tasks 
identified  for tritium in occasion of the "First Round Projects" 
launched in the frame of the 1982-86 research programme. The 
fundings attributed to each task and country are also indicated. 
For  comparison Table 2 gives an overview of the activities shared 
by the Commission's indirect action programme on tritium bearing 
waste from reprocessing of nuclear (fission)  fuel  in the frame of 
the "Management and Storage of Radioactive Waste" programme 
(DG  XII). 
1. 3 Summary of  past  and ongoing JRC activities related to  
tritium  technology 
Up to now the activities performed in this  field  pertain to conceptua 
design studies. The experimental work was  limited  to simulation 
studies  with  hydrogen and deuterium. 
In the  past  (1 978) a feasibility study of a process  similar  to the 

TSTA  (Tritium  System Test  Assembly)  of Los  Alamos  Laboratory 
has been commissioned to  SNIA  TECHINT,  Rome. The aim has 
been to  simplify  the process and in particular the isotopic se­
paration  system (ISS) by cryogenic  distillation  of the hydrogen 
isotopes and  helium.  A preliminary project of such a  facility 
together  with  a cost evaluation has been prepared by the  con­
tractor. 
In the meantime the concept of new processes was settled at 
the JRC Ispra  mainly  based on the handling of tritiated water 
with  the purpose to reduce the plant dimensions and consequently 
its investment and operational costs (especially for the secon­
dary  containment).  SNIA  TECHINT  again made a  feasibility  study 
of these  processes and a comparative cost evaluation  with  the 
first  study (1979)  confirming  the above assumptions. 
On the other hand the  tritium  inventory assumed  high  values in 
some processing units  (distillation  column  and electrolytic  cell). 
Experimental  work (1980) was started in order to demonstrate: 
. the  validity  of some separation factors between hydrogen 
isotopes reported in the literature; 
. the  possibility  of  realizing  an electrolytic  cell  with  low  liquid 
invento  ry. 
A new electrolytic  cell  has been successfully  tested  which  operates 
at high  current density (50  A/dm^)  with  the  liquid  inventory  main­
tained  at low values by soaking  only  the  separator  with  the elec­
trolyte.  Moreover,  with  the  same  electrolytic cellyvalues of the 
separation factor between protium and deuterium higher than 10 
have been obtained by using  iron  electrodes  confirming  the  best 
values reported in the literature. These studies are progressing 
in order to refine the performance of this new  cell  type. 

Presently,  in the  light  of some results obtained at  Garching  on 
the separation of (relatively) large volumes (400 cm^) of elemen­
tary hydrogen isotopes by gas chromatography a version of the 
JRC  process schemes  including  this technique is being  investi­
gated more deeply. 
A collaboration  with  IPP  Garching  on this process is envisaged. 
A comparative analysis of the safety implications of alternative 
processes has been started. 
Experimental  studies on hydrogen-metal interactions have been 
started at JRC Ispra during the last few years. In the experiments 
solution,  diffusion,  permeation, absorption and desorption of pro-
tium  and deuterium in various first  wall  candidate materials have 
been investigated. 
The  implications of  tritium  losses into  helium  as primary  cooling 
fluid  and its separation have been  assessed.  It was assumed  that 
tritium  will  be present  as tritiated water, due to the interaction 
with  the steam in the secondary  heat  exchanger. A suitable ab­
sorber has been studied in order to keep the  tritium  level  below 
those  required by safety considerations. 
Evaluation  of the  INTOR  tritium  losses through the  piping  of the 
cooling  systems has been performed using a code developed at 
Ispra. Several deuterium permeation  flux  measurements  through 
stainless steel membranes have been performed at different tem­
peratures  using an ultra  high  vacuum installation. Some measure­
ments  have been performed on  oxidized  membranes putting in 
evidence  the complexity of the problem of protective barriers. 

Theoretical  and experimental studies to investigate the  best  me­
thod to recover tritium from the  liquid  breeder  Li^yPbg^  are in 
progress at JRC-Ispra since some years. Measurements of hy­
drogen isotopes  solubility  on  Lij-^Pbg^  at various breeder tempe­
ratures  and gas  pressures  have been carried out first, in collabo­
ration  with  the University of  Cagliari.  Meantime the design of a 
facility  to demonstrate  the  validity  of a process layout based on 
tritium  extraction by a helium stream in countercurrent to the 
low-velocity  breeder  flow,  has been set-up. The construction of 
this  facility,  which  will  first  operate  .with  hydrogen, is scheduled 
by the second  part  of 1983. 
1. 4 Objectives of ETL 
There are common objectives to be achieved for the  fuel  cycle sys­
tems, to  which  the laboratory  will  be devoted: 
. acquire experience on handling tritium in complex systems in 
connection  with  the safety of operators during routine operation 
(general and  individual  protective means) as  well  as with  the pro­
tection of the environment  (waste  treatment,  emergency clean-up, 
monitoring); 
. provide the conditions to experience procedures for handling 
tritiated  parts  of the reactor and to optimize process components 
in relation to their operational safety and tritium inventory. In 
particular: 
a) execute experiments on tritium loaded mock-ups reproducing 
renewable  parts  of the NET reactor, aimed at decontamination 
and/or further  treatment  and conditioning (boots, seals, weldings); 
b) test  new concepts and components developed in the European 
laboratories,  like  gas chromatography, electrolyzers and 

catalyzers, tritium recovery systems from blanket in ad­
verse operating conditions and for  remote  handling; 
c) check the  validity  of the extrapolation of H/D physico-chemical 
data  to the tritium case. This experimental control  will  be 
performed with tritium at the  temperature  and  pressure  con­
ditions of fusion reactor applications, if  these  data  will  be 
not available as declassified information. 
To cope with  these  requirements, a multipurpose installation is 
required  rather  than a  facility  devoted to a specific problem 
such as for example  TSTA  (Los Alamos). 
1. 5 Laboratory layout 
ETL  should consist of a  hall  (see Appendix 1) acting as  ter­
tiary  containment for tritium with attached all necessary ancillary 
areas.  Experimentation of process units and systems (primary 
containment) are performed in dry boxes or caissons, placed in­
side the  hall.  They  represent  the secondary containment, equipped 
with  a proper clean-up system for on-line detritiation and recir­
culation  of its  atmosphere  in a closed circuit. For particular re­
search items requiring expensive and sophisticated instruments 
and equipment on one side and relatively small  amounts  of tritium 
on the other side, a few  individual  laboratories might be foreseen 
aside the  hall. 
ETL  can be located inside the protected  ESSOR  area, in the  vici­
nity  of the already existing stack (80 m height). The  hall  where 
the power supply for  SSTP  was foreseen can be  utilized  to install 
part  of the ETL facilities. 

Within  August 1983 a feasibility  study  with a preliminary  cost  eva­
luation  will  be performed including an estimation of the possible 
gain from the utilisation of the existing building with  respect  to 
a completely new realisation of the laboratory. 
1. 6 Tritium inventory 
Among  the  purposes  of ETL,the supply of tritium to European fusion 
machines  is not included. In an experimental  reactor  such as NET/ 
INTOR,  the  expected  tritium inventory  will  be of the  order  of se­
veral kilograms. As an example, in Table 3 is given the  break­
down of the tritium inventory  presented  in the INTOR-Phase Il-a 
European  report.  However, it  appears  that  the major  part  of this 
inventory  will  be present  as hold-up in  intermediate  storage  or at 
a stationary  state  in the blanket. In  TSTA  the  expected  tritium in­
ventory is 1 50 g. In  this  facility, which is devoted to a specific 
process,  a significant  part  of the inventory is  taken  by the cryodis-
tillation  column.  Given  the objectives of KTL, tritium inventories 
even lower, of the  order  of 50-100 g, should be sufficient for a 
significant operation.  These  values  correspond to  dose  committments 
in case  of accidental total  release  through  the  stack  in the form of 
tritiated  water  (which is very hypothetical), much below the value 
taken  as a  reference  in the existing External Emergency Plan of 
ESSOR. 
TABLE  3 -  Break-down  of the IIMTOR-lla tritium  inventory 
Plasma  exhaust  and  neutral  injectors 370 g 
Breeding  tritium 737 g 
Primary  coolant  detritiation 65 g 
Wastes not estimated 
Atmosphere 1 g 
Neutral  injectors  and  torus  feed 245 g 
1369  g 
Storage 2300  g 
Breeding  blanket 500-1000  g 
Total  ~ 4220-4720  g 

1. 7 ETL in the frame of the European activity on tritium 
As mentioned in the frame of the European  Fusion 
Technology  Programme 198Z-86, some activities are to be started 
dealing  with: 
. feasibility  studies of tritium recovery  from  fuel  as well  as from 
waste  streams  including  the air decontamination systems; 
. orientative studies on some components  like  electrolytic cells 
and tritium detection systems; 
. definition  of the actions for industrial development of large 
components. 
In the detailed  definition  of the tasks and the design of the JRC 
laboratory, a straight coordination and continuous exchange of 
information  will  be ensured  with  the other European laboratories in 
order to exploit and to integrate the results of  these  studies and 
to complement them. In particular the various proposed schemes 
and systems  could  be verified  with  accent on the operational con­
ditions  and safety (environmental requirements for example). For 
the laboratory construction,  full  utilization  will  be made of course 
of the parallel industrial development of components  (typically 
the case  of tritium compatible vacuum pumps and valves) foreseen 
in Europe. 
1. 8 Preliminary evaluation of time schedule and resources 
Starting  from  a possible  Council  decision, the  following  planning can 
be envisiiged for the design and construction of ETL: 
. 15 months for the detailed design of the basic laboratory  (hall, 
ancillary  equipment, secondary containment systems); 

. 36 months for the construction and mounting of basic omponents; 
. 6 months for commissioning  tests  and operation  start. 
The extension of the laboratory equipment to specific systems to 
test  processes and for mock-up operations should  start  two years 
after the beginning of the ETL design. 
This  time schedule  appears  to be in line  with  the  needs  of NET 
engineering design. 
The staff foreseen for the operation of ETL (beginning in all  cases 
in the multiannual plan after 1987) is estimated to be 2 5 research-
men, including 7 professionals.  During  the design and construction 
phase, the required JRC - staff  will  be about 8 research-Men/a for 
the 1984-87 programme. 
It is considered strongly recommendable to send, starting in 
1984, JRC personnel to  follow  the  TSTA  facility  operation in 
USA  (Los Alamos) for operation training. 
The cost of ETL is estimated to be 10-12  MECU  (1 983-value), 
6-8 MECU  of which  will  be for investments and contracts outside 
and 4 for staff and services. The  rate  of investments is: 
. 20% at the berinninp of the studv: 
. 60% after 15 months; 
. 20% during the  following  36 months period. 
1.9 Next  steos  of the  assessment 
1 . 
The actions for the  following  period (up to end August 1983) are: 
. design and cost evaluation of the  following  parts  of the  facility: 
a) technological  hall  including glove boxes, hot cells and other 
secondary containment caissons; 
b) specialized laboratories; 
c) auxiliary services (emergency clean-up system, glove box 
clean-up systems, hot ventilation, waste  treatments  and 
storage  area); 

optimization  of the emergency and glove-box clean-up sys 
terns  as a function of the programmed type of the  facility 
operation. 

APPENDIX  1 -  Preliminary layout of the ETL  facility 
ETL  is subdivided into two sectors: the Hot and  Cold  Areas. 
The Hot  Area  is formed by a technological  hall  (— 200  m2; 
h =10  m),  5 laboratories (~  20 each; h  = 4  m) and a service 
area  (= 160  m^) where the ventilation, clean-up and safety sys­
tems  are located. 
The  Cold  Area  includes offices and general services. 
The technological  hall  contains hot cells where tritiated (and 
eventually  activated) components can be remotely handled. 
Most  of the laboratories contain relatively  small  amount of  tri­
tium  (<10 Ci each) to perform basic studies, e.g. permeation 
tests,  thermo-chemical and kinetic properties. The other labo­
ratories  will  contain larger amounts of tritium  1000  Ci) to 
study  typical  processing  steps  such as electrolysis, chromato­
graphy. 
The service area  (200  m^) contains the normal and emergency 
clean-up systems serving the technological  hall  and the laboratory 
and the waste processing system. 
A preliminary layout is shown in the annexed drawing. The total 
surface of ETL is expected to be about  800  m^. 
As already  stated,  the area related to the technological  hall  is 
~ 10 m high.  The other  areas  have heights around  4 m. 

ANNEX  'Z: to  Ithe  -ttb Vhctm^ onlTrituia Hnnd 1 ijng-  Laboratory 

2. VIBRATING  TABLE 
2.1. Utilization  of Vibrating  Tables 
Today, there is an  increasing  concern  about the possible  effects 
of seismic events, or  similar  dynamic  phenomena  (e.g., airplane crashes, 
explosive  accidents, etc.) on both nuclear and  non nuclear, but 
potentially  dangerous,  industrial  plants, as well as on  civil engi­
neering  structures. 
The need for safety  assessments  and improved  design concepts in 
the above engineering  fields  has motivated the  development  of a wide 
spectrum of experimental and  analytical  research  activities  all over 
the world. 
In this context,  vibrating  tables represent  useful  and widely 
used experimental devices for  investigating  the behaviour of  structures, 
components,  or equipments  when submitted to  dynamic  loading. Their  range 
of capabilities  extends from in-depth  testing  of models  (e.g. to  validate 
calculation  methods),  to qualification  tests,  including  verification  of 
conformance  to prescribed standards. One may therefore  distinguish  be­
tween two fundamental  aspects in the use of  vibrating  tables: 
- testing  for qualification  purposes 
- testing  for research and  development  purposes. 
The latter  aspect includes a  wide variety  of possible  applications, 
such as 
study of  damping  characterist ics and frequency response' functions 
in the linear  and nonlinear range, 
study of coupled  problems,  such as  soil-structure  and fluid-structure 
interactions , 
assessment  of dynamic  behaviour and  extreme  load evaluation of  rein­
forced concrete  structures, 
. assistance in the  development  of antiseismic design concepts. 

- 2 -
2.2. Review of the existing vibrating tables 
A large number  of vibrating tables is currently in operation  through­
out the world.  In Table I we have reported the  main characteristics of 
some of the largest tables existing, or  under construction in the  Commu­
nity. For comparison  purposes  , we have also included in  Table I the per­
formances  of a Japanese  table which is by far the largest presently  under 
operation. 
From Table I it appears  that the size of the tables presently in 
operation within the  Member  Countries is in the  range of 0.5-25  m^ with 
a maximum  tested equipment  weight  of 5 to 25 metric tons. On the other 
hand the largest  facility  in the  world is a. 15x15m  table in  Japan which 
is capable  to test  equipments  weighting  up to 1000 metric tons. 
In addition to the  parameters  mentioned  in Table I, vibrating tables 
are also characterized by  their range of accurate  frequency  response, 
the number  of independent  loading directions, and  their capability of si­
mulating  complex  loading conditions  with an adequate  software. 
As far as the cost of vibrating tables is  concerned,  it appears 
to be difficult  to give precise figures. Tentatively one  might say that 
the cost of the  medium-size  vibrating tables presently in operation in 
the Community  is in the  range 1-5 MECU,  while, the large  Japanese  table 
could have a cost of  300-400  MKCU. The time schedule  for the design and 
construction of vibrating tables is  estimated  to be in  between  of 3 to 6 
years. 
2.3. Scope  of the JRC  assessment 
The JRC is currently trying to ascertain  whether  a vibrating table 
of intermediate size  between  the largest presently in operation in the 
Community  and the  huge Japanese  table may  respond  to the research and 
qualification  needs of the Member  Countries. 

- 3 -
TABLE T. : Shaking Table Performances (1) 
ORGANIZATIONS Table 
Name Degrees 
of 
Freedom Size 
m x m Force 
rating 
(kN) Max Tested 
Eqmt. weight 
(Metric Tons) Max-accele­
ration (g) Max-actuator 
stroke (mm) 
CEA, Saclay, 
France VESUVE 1 H 3.1x3.1 350 20 1.8g at 15t - 100 
CEA, Saclay, 
France TOURNESOL H 2 V 2x2 H 100 
V 2x100 10 0.9g at 10t H - 125 
V - 100 
Ansaldo Impianti 
Genova, Italy PERSEUS H 2 V 3.5x3.5 H 220 
V 208 10 1.7g at 2.5t H - 70 
V - 70 
Hochtemperatur 
Reaktorbau, 
Jülich, FRG SAMSON Hx 
3 Hy 
V 5x5 H 510 
V 850 25 1.5g at 25t 
2.Og at 15t 
3.0g at 5t - 200 
National Eng. 
Lab. Glasgow 
UK H 2 V 3 x 3 H 500 
V 3x250 20 H - 125 
V i 75 
National Eng. 
Lab. Glasgow 
UK H 2 V 3 x 3 H 150 
V 3x50 5 H - 125 
V - 125 
ISHES, Bergamo 
Italy T 1 
T 2 
T 3 2 
1 
1 2.5 x h 
0.62x0.62 
2 x 2 60 
15 
50 + 
- 35 
i 75 
* 125 
Technical Univ. 
Athens, Greece under 
construction Hx 
3 
Hy 
V k x 4 10 Hx:1.5g 
Hy : 1. 5g at 10t 
V : 2 . 9 g - 100 
Tadotsu Eng. 
Lab. Japan H 2 V 15 x 15 H 30000 
V 33000 1000 H 2.7g at 500t 
V 1.4g H - 200 
V i 100 
(1) A few typical tables are reported 

- 4 -
Apparently,  the construction of a vibrating table  with increased 
dimensions  could offer  advantages  such as: 
. reduction of the  problems  arising  from the impossibility to  complete­
ly satisfy the  laws of similitude in a scale  model, 
. possibility  to appraise  the response  characteristics  (damping,  frequency) 
at full excitation  level and to  analyse  the effects of nonlinearities 
induced  by the material  behaviour  and by  design  features  such as gaps, 
restraints,  etc., 
. possibility  to include in a  more realistic  fashion the coupling of the 
tested component  to its  environment, 
. possibility  to qualify  cumbersone  equipments (mechanical  or electrical )for 
which numerical  modelling  is particularly  difficult. 
However,  it must be kept in mind that the construction of a large 
vibrating  tabel represents  an operation of considerable technical and  eco­
nomical  relevance  and that its cost/benefit ratio  must therefore be  appraised 
in the necessary  detail. 
Another  aspect  to be kept in mind is the  very rapid development  of 
powerful  numerical  methods  for the simulation of  complex  dynamic  problems 
and the increasing  availability  of very large and fast  computers.  These 
developments  in software  and hardware  might well give the analysis a  much 
more important  role than heretofore and  consequently  reduce  the needs  for 
testing,  especially  with costly large-scale  models. 
The JRC is  shall analyze  further possible  community  needs for 
a vibrating table. If  such needs are identified the characteristics of 
a suitable table  will be determined. 
2.4. Status of the assessment  and further  steps 
The JRC is establishing a  number  of contacts  with organizations 
(e.g. industries, licensing  bodies,  possibly  insurance  companies) 
in the Community  potentially interested in the  development  of a project 
on a large vibrating table to be  installed  at Ispra. The JRC also  intends 
to confront the results of its  assessment  with those of similar studies 
presently in  progress  in some Member  Countries. 

- 5 -
Another  aspect to be considered in our evaluation is the  adequacy 
of the Ispra  site to host a large vibrating table.  Here, preliminary  indi­
cations based on previous experiences are that there should be no  major 
problems  as far as  availability  of space,  soil conditions and  power 
supply are  concerned. 
The possible  problems  for transport of very large  components  which 
cannot be assembled  or built on site will be investigated. 
If preliminary positive indications are obtained  from the above 
contacts, the JRC intends to  perform  under contract  more detailed enquiries 
and evaluations before presenting its findings on the  effective  needs for 
such a project and the results of the  feasibility  study. 
The outcome  of this study could be  made avalaible at the end of 1S84 at the 
earliest.At  that time the detailed elaboration of a  programme,  in colla­
boration with the  identified  interested partners could  start and lead to 
a final  proposal  about 18 months  later. 
In formulating  such a programme  the JRC should concentrate on  activities 
relevant to  Reactor  Safety and Industrial Risk.  Although  the JRC is presently 
not involved in seismic analysis,  competences  exist in the  areas of dynamic 
testing,  instrumentation, data acquisition and numerical  methods  which 
could be  used for the actions to be  proposed. 

3. INCREASE  OF JRC  ACTIVITY  ON  POST-JET  PROJECTS 
3. 1 Introduction 
Following  the  request  of the  Council,  two main projects have been 
considered: : 
. NET (Next European Torus), an experimental reactor project  which 
is included in the 1982-86 European Fusion Programme for  which 
a study team has been already  set-up  in Garching; 
. 1GNITOR.,  a high magnetic  field  Tokamak project  which  should 
prove the plasma  ignition,  the feasibility study of  which  has been 
done by an Italian team and evaluated by'an ad hoc Panel  set-up 
by the Commission. " 
1 * 
3.1.1.  NET 
In the current programme, JRC-Ispra is already  involved  in the stu­
dies of NET, as the main laboratory in support to the design team 
i 
set-up  at Garching, The participation to  these  studies  will  be increased 
in the next JRC cropramme (1984-871 namelv: 
. by a contribution to the conceptual design studies in the  areas  of 
mechanical  configuration and plant-layout, first  wall  and blanket 
components, safety and environmental analysis; 
. by the execution of a number of experiments in support to NET, re­
lated to materials investigation (first  wall  and breeder), major 
accidental  conditions and remote handling. In the  present  phase  of 
the NET studies this contribution covers the design  requests. 
As far as the problem of eventually hosting NET at Ispra is concerned, 
it appears  premature because, according to the European plan, the 
engineering design of this machine  could  not  start  before  1 988. 

3.1.2.  ICNITOR 
As it is well known, for the time being this project is not included 
among  those  submitted by the  Fucion  Associations and has not been discus­
sed by the Consultative Committee on Fusion Programmes, In  these  condi­
tions it is premature for the JRC to elaborate on this project.'What 
can be done is the evaluation of the feasibility of hosting such a project 
in Ispra and collateral impacts. 
3.1.2.1.  Summary of the characteristics of the  IGNITOR  project .. 
IGNITOR  is a Tokamak proposed by Prof.  Coppi  (MIT and Scuola 
Normale  Superiore di Pisa) in order to achieve ignition conditions. 
IGNITOR  has evolved from a line of high-field  devices  such as the 
Alcator  A and C and the  Fraacati  Torus.  In  Jl 9S0 a contract for a 
feasibility study was given by  CNEN  to.  Scu'oLa  Normale Superiore, 
this institute acting as main contractor on behalf of a study group in-
1 
cludine Tecnomasio Brown  Boveri.  CNR  Istituto  dei Plasmi di Mi-
lano,  NIRA,  Stone and Webster, SN1A Techint, etc. In May 1981 
the Feasibility Study was completed. At the end of 1982 an Ad Hoc 
• 
Review Panel appointed by the Commission of the European  Commu­
nities  examined the summary of the Feasibility Studv and pave an 
advice. .' | 
i 
i 
The main parameters of the machine are reported in Table 1. These 
parameters are not definitely sfcttled. • 
The  experimental  system  is composed of five main items: the ma-
• 
chine core  (4x4x4  m), the auxiliary heating  system  (RF), the  elec­
trical  supply system, the tritium aystem, the cryogenic  system  and 
other auxiliaries. The first three  items  cost  each about 1/4 of the 
total. The machine requires a biological shield about~Z'm thick and 
a remote handling system. 

3.1.2.2. Assessment  of the, feasibility of  Biting ICNITOR  at Icpra 
The main problems to be considered are : 
. electrical supply system 
. main  building  and  auxiliary  systems 
. licensing 
and , in addition : 
. fuel  handling, decontamination and waste  treatment  systens 
. ausxiliary systems 
. 'generic infrastructure support. 
Only  the first  three  items of this  list  have  bees  considered so far and 
the studies are proceeding, 
As working  hypothesis the  following  timing  has been assumed ;  three  years 
(83-86) for design and construction and  five  years (87-91) for the opera­
tion. 
A) Electrical  power supply 
The requirements of  IGNITOR  in terms of power transients demand 
are still  harder than those of JET (Table 1).  Bei^g  the electrical 
supply  a key issue for  siting,  highest priority has been given to its 
feasibility  and cost as sessment. Contracts have been esta­
blished  with  ENEL-Compartimento  di  Mi la no,  on the basis of a 
questionnaire  similar  to that  set-up  during the site enquiry for 
JET and on the basis of a preliminary design proposed by Tecnomaaio 
Brown  Boveri.  These contacts have confirmed the  feasibility  of the 
supply  directly  from  the  ENEL  380 kV  grid  at the border of the 
Ispra Centre. In the next days  ENEL  should send a. first detailed 
answer to the questionnaire  including  a preliminary cost for the 
line-up  to the main transformer station on the Ispra site, and the 
contractual conditions for the supply in the period 1957-1 59). 
The transformer station should be installed in the- Centre r.ear to 
the ESSOR  location. The time required for the re=."-izfctior. of the 
connection  and of the station is evaluated to be tv-c years. 

- L -
B. Building  and auxiliary  systems 
The best  location for  I^ITO:;  would be inside the  ESSO?.  protectee 
area.  An analysis of the possibility of installing the machine inside 
the main containment of  ESSOR  has shovn that this would not be ccn-
venier.t both  from  eco-^-ical and technical points of view. 
An area for a new building inside the  ESSOR  fence that offers opti­
mal conditions  from  the point of view of electrical connection,  buil­
ding  foundations , nuclear infrastructure and general infrastruc­
ture  has been identified. 
C. Licensing 
Ho major problems are.expected for licensing Indeed the  tritium  inven­
tory  in  ICTNITOK  should ~zt  exceed  1 g (]0,000'Ci;. 
The actual "release ferrule" for  gaseous  effluents frea  ESSO?.  rector 
jives  ar.-ual  release 200C Ci 
13 vee'-is period  JCOC  Ci 
successive  24 h period 4 Ci 
In caso  cf absolute  necessity  these  figures  csKi  be r=ultiplied by a factcr 5. 
In the  case  that  ESSOR  reactor  will  be decommissioned, the Licensing 
Authority  should be asked to  confirm  the existing release authorization. 
For the construction licence, a procedure similar to that adopted for the 
Ifipra  HC 40  Cyclotron  recently ir_stalled at Ispra ir. the fraae of the 
execution of the Fusion  ?rogram,  is required (arc. 55 D?F.  13.2.196^.  a. 185 
and DM  £.1.1977).  The licensing process is expected to take about 
tVD years. 
E) Collateral  aspects 
Studies should be contin^id. One can anticipate thr.t a nraber of require­
ments juch a machine cc-Id  find  s. proper environment within the JRC where 
appropriate  skills and s-.rppcrts have been develcppec in the framework, cf 
the pr:jtatre (reactor safety,  waste  disposal, 'fusim technology). 

5 -
3.5.  Further  Seeps  cf the Assessment 
For the  nest  step  (September) the activity  vijll  be : 
- Define  from,  a tecr.=i.cAl  and economical point of viev? the electrical 
supply  system 
- Define the overall layout of the buildings and auxiliaries and  provi­
de a prelim,inary caz evaluation •·.. 
- Check  with the  tel?  cf Prof.  Ccppi  or. the  cost  recent version of the 
design of the  m*c'mim£,  further requirements' of che  site. 
- Define and evaluate in detail the  steps  of the licensing procedure. 
i 
I 

Table  1 - Power  Supply Requirements 
IGNITOR 
Total energy consumption pulse  (GJ)  0.4 -  0.006 
(Toroidal  and  Poloidal Field Coils) 
Pulse  duration: 
• raise  time  (sec)  2 
- plateau  time  (sec)  1 
Required pulse power: 
- active  (MW)  600 
- reactive (MVAR)  500 
Pulse  frequency  (max) '  3/d'"-
Max number  of pulses 
- max. power 
T low power .5.000 
50.000 JET 
5.3 - 1.0 
13 
20 
575 
300 
6/h 

APPENDIX  I - IGNITOR Reference Specifications 
Geometrical 
Parameters Symbol  Pre-compression Post-compression 
Major radius (cm) 
Minor radii product (cm2) 
Plasma  current (MA) 
Toroidal magnetic fiel d 
at R = R0 (kG) 
Average  beta <ß> 
Primary plasma heating 
method 
Auxiliary heating 
(LH.  or I.CR.H.) 
Peak plasma density nQ 
Neutron wall loading . 
Maximum number of neu-
tronsper discharge 
Operatiorial  life span 
Tritium  injected (per 
discharge) 
Toroidal field pulse 
length  (flat  top) R.0 
a,b 
B11 
B 109 
30.5 x 38 ( 
2.6 ' 
80forq^=»2 
100 forq^.5 
Bei ow 1 % 72.5 
25 x 31 
4 
120for q^=2 
150 for q^~ 2.5 
Ohmic  and adiabatic comr->ression 
5 MW  with  0.4 sec pulse length 
~ I0is/cm3 in post-compijession phasö 
~ 1.6 MW/m2 
5x 10'8 -* 
5 years 
15 curie 14 MJ of thermonuclear energy 
1.5 sec at 120 kG 
1 secat 150 kG