CEA - Robatel

1
INTRODUCTION
•PRÉSENTATION
P. 3 to 9
ENGINEERING | DESIGN | CALCULATIONS
•INGÉNIERIE | ÉTUDES | CALCULS
P. 10 to 13
TURNKEY PROJECTS
•ENSEMBLIER
P. 14 to 24
HOT CELLS
•CELLULES BLINDÉES
P. 25 to 28
GLOVE BOXES
•BOITES À GANTS
P. 29 to 32
CASKS
•EMBALLAGES
P. 33 to 50
NEUTRON THERMAL PROTECTIONS
•PROTECTIONS NEUTRONIQUESP.
THERMIQUES
51 to 55
2
DOORS HATCHES
•PORTES | TRAPPES
P. 56 to 58
METAL WORKING
•CHAUDRONNERIES DES MÉTAUX
P. 59 to 61
ASSISTANCE | SERVICES
•ASSISTANCE | SERVICES
P. 62 to 67
3
French company set up in 1830
Involved in the nuclear field since 1953
LOCATIONS :

Rue de Genève - BP 203
69741 GENAS Cedex
Tel. 00 33 472 22 10 10
Fax 00 33 478 90 23 79
commercial@robatel.fr
Capital of 1,800,000 Euros
La Hague 
100 % subsidiary of ROBATEL SA

Turnover > 19 M€
Marcoule 
Cadarache 
www.robatel.fr
La Hague
Z.I. de Digulleville
50440 BEAUMONT-HAGUE
Tel. 00 33 233 01 80 00
Fax 00 33 233 04 09 57
lahague@robatel.fr
> 120 employees
Genas (headquarters) 
Genas (headquarters)

Marcoule
Z.I. de L'Ardoise
30290 LAUDUN- L’ARDOISE
Tel. 00 33 466 50 49 20
Fax 00 33 466 50 30 80
marcoule@robatel.fr

Cadarache
Zac du Pas de Menc
83560 VINON SUR VERDON
Tel. 00 33 492 70 63 35
Fax 00 33 492 72 28 19
cadarache@robatel.fr
4
► Genas
headquarters
► Establishment
of Cadarache
ROBATEL
Technologies, LLC
Established in 2009


Subsidiary of ROBATEL SA,
In charge of the ROBATEL Group’s
development on the American nuclear
market.
LOCATION :
 ROBATEL Technologies, LLC
5115 Bernard Drive, Suite 304
Roanoke, VA 24018
Tel.: 001 540 989 2878
sales@robateltech.com
► ROBATEL
5
Technologies
ROBAT
EL
Techn
ologies
Roanoke
Our skills
6
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Design, calculations, studies,

Turnkey projects,

Metal working,

Mechanical engineering,

Lead working,

Site operations.
Company’s certifications

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
CEFRI
no. 348 E Management of staff category "A" or "B" working under radiation,
ISO 9001 / 2008
Quality Management in the design, manufacturing, installation, maintenance of
equipments for industry and research in the nuclear field,
Since 2010, ROBATEL is authorized to use decontaminated lead outgoing from
CEA,
CAEAR
Notification of acceptance for the following areas :



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MASE certification (Improvement Manual Enterprise Security),
EDF
Certificate of qualification to perform services
in the following EDF qualification systems :

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


7
Genas : Domain D 4-2E “Assistance in work control and occasional design studies”,
La Hague and Laudun : Domain D 3-1 «Intervention environment according to the radiation protection
of the regulated area»,
Activity on fuel,
Nuclear logistics maintenance,
Intellectual services and technical assistance,
Transport,
QA/QC capabilities: NQA-1 & 10 CFR Part 71.
► Obtaining
the Label supplier AREVA
Our main French
customers


AREVA (AREVA NC, AREVA TA, AREVA NP,
TNI, SGN, MELOX, STMI, AREVA MED, FBFC,
CERCA)
CEA (CADARACHE, FONTENAY-AUXROSES, GRENOBLE, LA HAGUE,
MARCOULE, PIERRELATTE, SACLAY,
VALDUC, BRUYERES-LE-CHATEL)
EDF (AMI – DAC – UTO – CIDEN – CNPE –
DCN)
ANDRA,

AIRBUS Defence & Space (ASTRIUM),


ALSTOM, BOCCARD, BOUYGUES, CAMECA,
► Radiation
shielding of the French nuclear-powered
submarines
CEGELEC,CIS BIO,CNIM, DAHER,
DCNS,DGA (Délégation Générale pour
l’Armement),ENDEL, IRSN,GROUPE
ONET,GANIL, LINAC,NUVIA, SPIE,
SYNCHROTRON SOLEIL …
8
Some of our customers abroad
9
AUSTRALIA
 ANSTO
BELGIUM
 ONDRAF / Institut des radioéléments
(IRE) / IBA / SCK CEN /
TRANSNUBEL / BELGOPROCESS,
SYNATOM
BRAZIL
 CTMSP
CANADA
 TRIUMF
CHINA
 China nuclear industry huaxing
 China nuclear energy industry corp
 TNPJVC
CZECH REPUBLIC
 Nuclear Research Institute
EGYPT
 Atomic Energy Establishment
GERMANY
 Babcock Noell
 ITU
GREAT BRITAIN
 BNFL
ITALY
 EURATOM, Ispra / CNEN, Rome
JAPAN
 Tokai Mura / JNFS
MAROCCO
 CNESTEN
NETHERLANDS
 Energy research Centre of the Netherlands
NORWAY
 ABB Norsk Kabel
 ALGETA
RUSSIA
 ZVEZDOTCHKA (Shipyard in Severodvinsk)
SOUTH KOREA
 KAERI
SWEDEN
 SKBF
SWITZERLAND
 ZWILAG
UKRAINE
 UKRATOMINSTRUMENTS
U.S.A.
 SHAW AREVA MOX SERVICES LLC (JV)
 Department Of Energy
 Premier TECHNOLOGY Inc.
 U.S. ITER Project Office
 WCS
 EXELON
10
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Preliminary design,
Studies of turnkey for
completes installations,
Feasibility studies.

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Mechanical calculations,
Thermal calculations,
Radioprotection calculations,
Criticality calculations,
Crash calculations.
OUR SOFTWARE MEANS :



2D CAD: Autocad,
3D CAD: Solidworks, Spaceclaim,
Calculations :



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

11
Mechanical finite elements analysis:
ANSYS 15.0, Cosmosworks
Crash calculations:
LS-DYNA V971 R7
Thermal finite elements analysis:
ANSYS 15.0
Neutron and criticality calculations:
TRIPOLI 4.3.2 / SCALE 6.1
Radioprotection calculations:
TRIPOLI 4.3.2 / SCALE 6.1 / MICROSHIELD 6.10
Various analytic calculations (strength of materials, thermal, containment, …): MATHCAD 2001
Example of tradeoff study followed
by manufacture
VERDON laboratory,
CEA Cadarache
12
PRELIMINARY STUDY FOR THE
CONSTRUCTION OF A LABORATORY,
TAKING INTO ACCOUNT THE
FOLLOWING AREAS :

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
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

Civil engineering,
Seismic calculations,
Electricity high and low voltage,
Drive control – automation,
Ventilation,
Handling equipment,
Mechanics, metal working,
Future maintenance and operation,
Risk analysis,
On site assembly and testing.
Preliminary study
example
Mo / Tc laboratory, CIS
BIO Schering
PRELIMINARY STUDY FOR THE
CONSTRUCTION OF A LABORATORY,
TAKING INTO ACCOUNT THE
FOLLOWING AREAS :





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
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Nuclear and pharmaceutical regulations
(GMP),
Production rate criteria,
Interface civil engineering / new building,
Control – automation,
Electricity high and low voltage,
Ventilation,
Handling equipment,
Mechanics, metal working,
Future maintenance and operation,
Risk analysis.
14
CEA STEMA facility located in Marcoule, France
A process system for the treatment of liquid
effluents utilizing an full feature cementation line to
include :
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15
Automatic transfer of new drums,
Automated drum handling, positioning, self cleaning of the
cementation injection line, filling, vibration packing/settling
system,
Automated recovery of the injection line cleaning water,
Package drying and inspection,
Preparation and filling of the drums with non active morter cap
or sealing layer,
Automatic placement and crimping of the drum lid,
Computerized drum inspection after filling, curing and sealing,
Automated drum radiation mesurement,
Storage carousels / transfer station for the placement of a
sealed drum into a transport cask,
ICC, wiring and command control system incorporated into the
process line.
Turn-key
installations
Waste sorting and
conditioning unit,
EDF/AMI Chinon
This unit allows to sort waste thanks to a shielded tight
cell equipped with remote controlled robotized handling
means.
These waste are sorted according to their physicochemical properties and radiological characteristics.
Then, they are reconditioned for shipment to ANDRA’s
or other sites.
THIS INSTALLATION IS COMPOSED OF THREE
AREAS :
 A sorting cell made of concrete, totally lined with a
stainless steel sleeve, equipped with telemanipulators,
an overhead crane, a cutting press, and a spectrometry
control station. This cell is a fire-barrier with regard to its
environment, and is dimensioned to stand a seism,
 A loading/sealing station, with conveyors and
elevators for leading new drums under two tight hatches
communicating with the sorting cell, and two drum
sealers,
 An evacuation lock-chamber equipped with an
automatic device measuring the contamination by
rubbing.
16
Waste sorting and conditioning unit, EDF/AMI Chinon
17
Radioactive waste
cementation unit,
ZWILAG
(Switzerland)
MAIN OPERATING FUNCTIONS :






18
Reception and storage of various
concrete components,
Eventual pretreatment of some
homogeneous waste,
Preparation of the concrete (mixing),
Draining of the concrete into drums or
transfer towards concrete work
stations,
Cleaning of the injection system, and
recovery of the rinsing effluents,
Transfer, drying and control of the
drums.
Outstocking of plutonium packings
contained in drums located at the
« Pégase » regulated nuclear
facility of CEA CADARACHE
MAIN FUNCTIONS
PROVIDED :

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
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
19
Outstocking of over 2,700
drums through packaging
developed to meet the safety
criteria,
Transfer with sealing of the
packagings drums to gloves
boxes,
Measures and wastes
characterization,
Compaction of empty drums,
Injection of mortar in 870 liters
drums containing the wastes,
Evacuation of drums to
storage,
Aim of the project: 2 years to
develop, manufacture and
installation. 3 years of
operation.
Equipment for MOX fuel production plant
► Rods
final inspection
and sorting
► Rods
► Powders
handling
20
► Filters
decontamination
storage and
► Rods
handling carriage
pre-clogging
Incineration and cementing unit for very low level waste - Shipyard in
Severodvinsk, Russia
► Factory
► Pushrod
system
for ashes
21
► Incinerator
assembly
► Bicarbonate
injection station
► Station
for introduction of
ashes, cement, bentonite and
water
► Station
for preparation of
cement and bentonite
► Ceramic
filter
AGATE, CEA Cadarache :
Glove boxes of samples-taking,
pneumatic transfer and distribution of
pitchers
SCOPE OF PROJECT :




22
Integration of part of the
process of the Advanced
Management Workshop and
Effluent Treatment,
Design, manufacturing,
installation on site, testing and
commissioning of a set of four
glove boxes (calculated
earthquake) automated
sample-taking, connected by a
network of pneumatic transfert,
Integration of all automated
mechanical elements and
control systems,
Supply and installation of
sorbonnes.
Equipment for French DCN
► Shielded
shell
Mass 70 tons
23
► Tooling
K15
Mass 90 tons
► CEA
Design, manufacture, assembly
and tests of a loading and
unloading platform for type B
casks
► CEA
► EDF
Design, manufacture,
assembly and tests
of a radioactive
waste cementation
unit
24
► Docking
Valduc
Collimator
for drums with the holding and the
sealing of the lid
► CEA
Specific device used for transfer, control and reconditioning
of waste containers from storage pit
► CEA
Remote
intervention for
cutting in a
contaminated
environment
25
Design, manufacture
and assembly


2
Photo credit :
P.Stroppa / CEA
► Atalante
Designer and manufacturer of hot cells
since the 60s,
ROBATEL Industries still develops new
techniques and improves its skills in the
field of design and manufacture of hot cells.
26
Design, manufacture
and assembly
►
► Hot
cell for
Cyceron
27
3 cells for IRE, Belgium
►

Last references 2002 / 2006.
► Hot
cells for SCK CEN,
Belgium
► Hot
cells for the nuclear center
of Morocco
Supply of 1,800 tons of lead shielding for
the CEA Saclay (PELECI)
► Hot
cells for SCK CEN,
Belgium
► Hot
cells of LECA, CEA Cadarache
Design, manufacture
and assembly
► Pharmaceutic
cell
Cis Bio (IBA)
► IRE
(renovating)
28
► Neutron

cell (PNT7™ Robatel) CEA
► Cell
for microprobe
Karlsruhe
Saclay
► AREVA
MED cell
Last references 2007 / 2013.
► ANSTO
cell
► ALGETA
► Cadecol
cell on SCK plant
cell (CEA)
29
Study, manufacture, assembly
► MELOX
► MELOX
► CEA
► CEA
► CEA
► CEA
30
► MELOX
► COGEMA
► ZWILAG
Photo credit : P.Dumas / CEA
Study and manufacture of internal equipment
► MELOX
► AREVA
► IRSN
31
► ALL
FILL (GB)
NC
► CEA
Glove boxes dedicated to a US MOX plant
► Separating
32
Hoppers Glove Boxes
33
Design & approval
Starting with the first
French reactor “ZOE”:
60 years of experience
► Underwater
► Shuttle
for vitrified HLW
Transportation of a
1300 MW PWR fuel
assembly
► R52
► R62
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34
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Design and acquisition of 78 approvals of
type B transportation casks,
Design of many casks: type A, IP2, …
Extension of approvals,
Elaboration of special arrangements.
ORIGINAL TECHNICAL PATENTED :
 Neutron-absorbing and thermal protections:
compounds ROBATEL no 9™, 10™, 21™,
22™, PNT7™, PNT3™,
 «Thermal switch » protection,
 Tightness by triple seals,
 Transport frame.
► R72
Scale models - drop
and fire tests
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►9
35
meters drop test of a scale model of a type B cask:
 Movies of the falls using high speed cameras
 Instrumentation of test specimens (accelerometers ...)
Design and manufacture of scale models,
Drop tests carried out on our In-house
approved drop test facility,
Performance of fire tests (800°C/1 472°F, 30 min).
►9
meters drop test of a scale model of a type B cask:
ROBATEL drop test facility approved by the French
nuclear safety authority (ASN)
Design &
manufacture
Over 1000 casks
36
R68 cask
Transportation of concrete shells
for EDF (type B cask)
► Stowage
Specificities:

Very sturdy
containment system
(100 mm of stainless steel)

Very large loading
capacities
(2 150 L / 6 300 kg)
► R68
Main package dimensions:
Radiological protections:
 Height:
H 2 240 mm (7,4’)
 Side (steel) :
 Diameter:
Ø 2 450 mm (8,0’)
 Upper/lower sides (steel):
 Gross weight:
20 600 kg (45 415 lbs)
Drop tests
 Cavity height:
H 1320 mm (4,3’)
 Cavity diameter:
Ø 1 440 mm (4,7’)
 Cavity Volume:
 Maximum payload:
de 100 à 120 mm (3,9’’ to 4,7’’)
Others protections:
 Compound ROBATEL PNT7™
Loading capacities:
► R68
Drop test specimen
2 150 L
6 300 kg (13 890 lbs)
130 mm (5,1’’)
(thermal)
30 mm (1,2’’)
Approvals:
 UN 2916 - Type B(U) : ADR
Applications:
37
37

Transportation of activated and contaminated waste type filter or metal,
packaged in concrete shells type C1 or C4
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Transport mode: road
Maximum activity:
120 A2
Maximum γ activity:
31 TBq (Co60 equivalent)
R72 cask
Spent fuel rods transportation (type B cask)
Main package dimensions:
Radiological protections:
(lead equivalent)
 Length:
L 6 255 mm (20,5’)
 Side:
> 180 mm (7,0’’)
 Diameter:
Ø 1 680 mm (5,51’)
 Front:
> 300 mm (11,8’’)
21 500 kg (47 400 lbs)
 Rear:
> 290 mm (11,4’’)
 Gross weight:
Loading capacities:
 Cavity length:
 Cavity diameter:
Others protections:
L 5 330 mm (17,5’)
Ø 140 mm (5,5’’)
 Cavity volume:
 Maximum payload:
80 L
650 kg (1 430 lbs)
(neutron / thermal)
 Compound ROBATEL PNT7™ 210 mm (8,3’’)
 PEHD
Approvals:
(France + Validations abroad)
 UN 3329 - Type B(M) Fissile : ADR + RID
Applications:

Transportation of 10 highly irradiated spent fuel rods
for R&D needs:
•
•
•

International transports from the PWR facilities to the research
laboratories:
•
38
38
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Rods types: UO2 or MOX,
Rods from PWR 900, 1300 or 1450 MW,
Compatibility with EPR rods.
France, Italy, Switzerland, Germany, Sweden, Denmark, Spain…
Transport modes: road or rail.
Spent fuel rods:
UO2
Number of rods :
Burn-up :
Cooling time:
U235 enrichment:
Pu rate:
MOX
≤ 10
≤ 100 GWd/tHM
≥ 6 month
≤ 10%
≤ 1,5%
-
≤ 15%
R72 cask
Spent fuel rods transportation (type B cask)
Specificities of the cask:
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Double sealed enclosure controlled and resistant to accidental events:
•
•
Cask’s cavity closed and sealed by 2 closure lids (front and rear),
Independent internal canister: closed by a sealed shielded plug,
Loadings/unloadings allowed under water:
•
•
By immersion in a pool,
By interfacing to a sas under a pool,
Loadings/unloadings in vertical or horizontal positions allowed,
Has a transport frame allowing it to tilt,
Has all the tools specifically dedicated to its operation.
Drain port
Cask body
Front shock absorber
Front sealed closure lid
Canister sealed & shielded plug
Front
Rear
Trrunions for
handling and tipping
Sealed canister
Stowage element
Rear sealed closure lid
Basket (capacity : 10 PWR rods)
Rear shock absorber
39
39
Tightness flange
► Transport
frame of
the R73 cask
R73 cask
Transportation of activated/contaminated
metallic waste from EDF NPPs dismantling
(type B cask)
Main package dimensions:
Radiological protections:
(lead equivalent)
 Height:
H 2 370 mm (7,8’)
 Side:
> 220 mm (8,6’’)
 Diameter :
Ø 2 210 mm (7,3’)
 Upper side:
> 270 mm (10,6’’)
23 900 kg (52 690 lbs)
 Lower side:
> 185 mm (7,3’’)
 Gross weight:
Loading capacities:
 Cavity height:
 Cavity diameter:
 Cavity Volume:
 Maximum payload:
Others protections:
H 935 mm (3’)
(thermal)
 Compound ROBATEL PNT7™ 30 mm (1,2’’)
Ø 1 040 mm (3,4’)
790 L
2 250 kg (4 970 lbs)
Approvals:
 UN 2916 - Type B(U) : ADR + RID
Applications :
► 17
40
40
packagings manufactured

Transport of metallic activated and contaminated waste (HLW and ILW)
from the dismantling of the Nuclear Power Plants (1rst generation),

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
Transport modes: road or rail,
Maximum activity:
6 500 A2 / 12 700 TBq,
Maximum γ activity:
2 000 TBq / 1 TBq/kg (Co60 equivalent).
R73 cask
Transportation of activated/contaminated
metallic waste from EDF NPPs dismantling
(type B cask)
Handling devices
for the upper shock
absorber
Upper shock absorber
Depressurisation plug
Tightness control plug
Sealed closure lid
Specificities of the cask:
41
41
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Very high loading capacity ( 2 250 kg (4 970 lbs) / 790 L),

Able to load the waste « in bulk »,

Very important shielding,

Presence of a secondary shielded plug equipped with
seals under the closure lid which ensures :
• the protection against the radiations and,
• the containment of the activity,
even at the opening of the lid,

Has a specifically designed transport frame equipped with
certified ISO corners,

Has all the tools specifically dedicated to its operation.
Handling device
for the shielded plug
Secondary shielded
plug
Metallic basket
Upper shock absorber
fastening support
Handling devices
of the cask
Cask body
Lower shock absorber
fastening support
Lower shock absorber
R74 cask
Design, approval, manufacturing of 2 type B(U) casks R74 for wastes
transportation Scotland (Dounreay) / Belgium (SCK)
Main package dimensions:
Radiological protections:
 Height:
H 2 350 mm (7,3’)
 Side:
 Diamter :
Ø 2 710 mm (9,0’)
 Upper side:
> 105 mm (4,2’’)
24 500 kg (54 080 lbs)
 Lower side:
> 120 mm (4,7’’)
 Gross weight:
Loading capacities:
H 1 320 mm (4,4’)
 Cavity diameter:
Ø 1 780 mm (5,9’)
 Maximum payload:
 UN 2916 - Type B(U) : ADR + RID + IMDG
Others protections:
 Cavity height:
 Cavity volume:
Approvals:
> 85 mm (3,4’’)
(thermal)
 Compound ROBATEL PNT7™ > 30 mm (1,2’’)
3 285 L
4 280 kg (9 430 lbs)
Applications:
 Cimented waste from the reprocessing of spent fuel,
 Very large loading capacities ( 3 drums of 500L),
 Transport modes: road, rail and maritime,
 Transport frame equipped with certified ISO corners to
facilitate the transportation.
Content:
 Maximum activity : 80 TBq / 320 A2,
 Maximum g activité: 75 TBq (Cs137 equivalent).
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42
(lead equivalent)
R75 cask
Design, approval and manufacturing of a type B cask for the
transportation of 5 cluster guides for EDF UTO
Applications:

Transport of 5 irradiated cluster guides:
• Activated and contaminated metallic pieces,
• From 900, 1300 or 1450 MW PWRs,

Optimized shielding relative to the specific activation profile of the
cluster guides,


Loadings / unloadings performed under water in vertical position,
Transport frame equipped with certified ISO corners allowing the
tipping of the cask in vertical position.
Main package dimensions:



 Length:
L 4 755 mm (15,6’)
Transport mode: road,
 Diameter:
Ø 2 100 mm (6,7’)
Total activity: 13 A2,
 Gross weight:
Maximum γ activity:
Loading capacities:
(Co60 equivalent )
•
•
10 TBq,
80 GBq/kg.
24 080 kg (53 090 lbs)
 Cavity length:
L 4 540 mm (14,9’)
 Cavity diameter:
≥ Ø 880 mm (2,9’)
 Cavity volume:
 Maximum payload:
43
43
Radiological protections:
3 000 L
2 225 kg (4 905 lbs)
 Side:
Front zone:
Rear zone:
(lead equivalent)
> 62 mm (2,4’’)
> 130 mm (5,1’’)
 Front:
> 170 mm (6,7’’)
 Rear:
> 145 mm (5,7’’)
Others protections :
(thermal)
 Compound ROBATEL PNT7™ 35 to 103 mm
Approvals:
 UN 2916 - Type B(U) : ADR
R76 cask
Design, approval and manufacturing of 4 Type B casks for the
transportation of waste drums for CEA Cadarache
Main package dimensions:
Radiological protections:
 Height:
H 2 215 mm (7,3’)
 Side:
> 185 mm (7,3’’)
 Diameter :
Ø 2 210 mm (7,3’)
 Upper side:
> 200 mm (7,9’’)
20 150 kg (44 420 lbs)
 Lower side:
> 300 mm (11,8’’)
 Gross weight:
Loading capacities:
 Cavity height:
 Cavity diameter:
Others protections:
H 655 mm (2,15’)
 Maximum payload:
 Compound ROBATEL PNT3™ 38 mm (1,5’’)
620 L
> 920 kg (2 030 lbs)
Content:
 Maximum activity:
36 000 A2 / 100 A2/kg
Approvals:
 Maximum γ activity: 125 TBq (Co60 equivalent)
 UN 3329 - Type B(M) Fissile : ADR
 Fissile material:
Applications:

Transports by road of 2 to 5 technological waste drums (HLW & ILW):
• Contaminated and activated waste / Materials: metallic, minéral and organic,
• 60 to 200 L drums  Modular internal fittings (metallic baskets, shielded plugs…),

Very sturdy containment system:  Withstands an hydrogen internal explosion*,

Large loading capacities and important shielding + Secondary shielded plugs:
 Protection retained even when loading/unloading the drums.
* (shown by explosions experimental testing)
(thermal)
Ø 1 100 mm (3,60’)
 Cavity volume:
44
44
(lead equivalent)
≤ 210 g
R77s cask
AREVA NC
Design and manufacturing
of a site cask for the
transportation of 4 drums
of alpha wastes
Gross weight:
3 500 kg
(7 720 lbs)
Maximum payload:
725 kg
(1 600 lbs)
45
45
RT100 cask
WCS (USA)
Design, approval and manufacturing
of 4 type B casks
for the transportation of
class B & C waste
Gross weight:
41 500 kg
(91 500 lbs)
Maximum payload:
6 800 kg
(15 000 lbs)
46
RTG32s / RTG33s casks
EDF UTO
Design and manufacture
of 9 casks to store 32 or 33
clusters guides
Gross weight:
57 000 kg
(125 700 lbs)
RA03 cask
EDF CIDEN
Design and manufacture of a cask
for the transportation of the lid of
the vessel of Chooz A reactor
Gross weight:
74 000 kg
(163 150 lbs)
47
47
R69s cask
CABRI, IRSN Cadarache
Transportation package
for R&D spent fuel
Approvals:
 Transport on Site – Class 3 – Fissile
Main properties of the cask:
 Length:
L 8 400 mm (27,6’)
 Diameter:
Ø 2 400 mm (7,9’)
 Gross weight:
42 500 kg (93 700 lbs)
 Maximum payload:
24 500 kg (54 000 lbs)
 Maximum activities: 1 250 A2 (10 000 A2/kg)

Transfert cask:
• Loading / Transfert / Unloading of an experimental device
containing one spent fuel rod from the CABRI
research reactor
(UO2 or MOX, Burn-up ≥ 90 GWd/tHM ,Cooling time ≥ 24 month,
Length: 560 mm (22’’)),
•

48
48
Protections: Radiological / Containment,
Transportation overpack:
• Transport on site of the transfert
cask loaded with the experimental
device,
• Internal stowage systems,
• Protections:
- Radiological,
- Mécanical,
- Thermal,
- Containment.
 Fissile material:
Protections:
(radiological / neutron / thermal)
 Steel:
50 mm (1,6’’)
 Lead:
95 mm (3,7’’)
 Compounds ROBATEL :
► Transportation
(or overpack)
► Transfert
≤ 35 g
cask
(and internal stowage devices)
hull
PNT3™ et PNT7™
Crédit photo : CEA
Other recent references:
– Design of type B
cask for liquid radwaste
► CEA
► EDF
► EDF
49
49
– 30B and 48Y Casks (2010)
(UF6 transportation)
– Design and approval of a type B cask
for the transportation of concrete shells
► CEA
– Design and manufacture of cask for contaminated glove boxes
transportation
Other recent references:
► EDF
CIDEN
Design and certification of casks family for
the Superphénix’s PNL transport, storage
and disposal :
Manufacture of 58 casks
► CEA:
► CEA:
50
50
R64 Type B cask: transport of neutron sources
Phénix cask
► CEA:
Pégase container
51
Compound
ROBATEL no. 9TM
and no. 10TM
► Wall
52
CP9 (PPB)

With a binder based on plaster, these neutron
materials can be used for any protection which does
not support any thermal or any particular
mechanical constraints.

It is always placed in metal casing, hermetically
closed so that it maintains its optimal characteristics.
In this case, access to the interior of the casing at
the time of implementation should be as broad as
possible. In the absence of containment, it should
take account of the gradual loss of the free water by
drying.

This type of material was subject to irradiation tests
until a fluence of 1,8.1017 thermal neutrons/cm². No
apparent degradation was observed.

Chemical composition: boron, calcium, carbon,
hydrogen, oxygen, sulfur, miscellaneous.
Density : 1,15 to 1,25 g/cm³.
Material approved by : CEA, AREVA, EDF.
Compound
ROBATEL no. 21TM
and no. 22TM
53

Neutrophage materials made of a base of polyester
resin. They have independent properties to any
containment. They are generally molded to the
shape and size desired and can be, if necessary,
machined.
They enable to make protection with a high
mechanical strength and good heat resistance.

This type of material was subjected to irradiation
testing until an integrated flux of 1,4.1018 thermal
neutrons/cm². No apparent degradation was
observed.

Chemical composition: aluminum, boron, calcium,
carbon, chlorine, hydrogen, oxygen, miscellaneous.
Density : 1,20 to 1,30 g/cm³.

Material approved by : CEA, AREVA, EDF.
Facilities for 26 reactors in France, 1 in Korea, 1 in
South Africa and 22 in China.
Compound
ROBATEL PNT7TM

These neutron-absorbing materials are as fine
mortar and may be used for any protection
subjected to thermal and mechanical stresses. They
are preferably introduced in metal boxes, closed
tightly so that they retain its optimum characteristics.
In the absence of containment, it should take
account of the gradual loss of the free water by
drying. The crude mortar exactly reproduces the
surface of the mold. Its ease of decontamination can
be improved by applying a surface coating. This
material is classified M0.

Chemical composition: aluminum, boron, calcium,
iron, hydrogen, oxygen, miscellaneous.
Density : 1,75 to 1,95 g/cm³.
Material approved by : CEA, AREVA, EDF, US
Department of Energy.
(Thermal Neutron
Protection no. 7)
and PNT3TM
54
NEUTRON AND GAMMA
PROTECTIONS
EPR TAISHAN 1&2
55

Design, calculation and manufacturing of neutron
and gamma protections for the two EPRs to China.
56
Over 1200 tons produced since 2000
Design, manufacture, shop and site assembly
► Lead
57
shielded door IRSN
► Shielded
hatch installed at
Chernobyl
► Shielded
hatch Belgoprocess
Recently manufactured :
► Shielded
hatch (7 tons) for Chernobyl
► Hatch
58
► Motorized
shielding (50 tons) for the anti-neutron protection
of a cyclotron (Milan, Italy)
in hot cell
► CEA
Saclay STELLA building
► Motorized
doors for BELGOPROCESS (Belgium)
59
Stainless steel
and metal
working
MATERIALS
 Stainless steel: austenitic, superaustenitic,
refractory,
 Aluminum and alloys,
 Titanium and alloys,
 Nickel and alloys (Monel, Inconel, Hastelloy…).
CODES CARRIED OUT
 CODAP, ASME, RCC-M, RCC-MR, RCC-MX.
► Lid
60
for Phénix (RCCM-R)
► 65
ton sleeves for nuclear fuel loading pools,
DCN
► 16T
forged device - CEA
Stainless steel
and metal
working
OPERATING MODES QUALIFICATION
 References : NF EN 288.3, ASME, RCCM…
 Number of reports : over 180,





stainless steel : 304L, 316L…
heavy steel : U45N, UB6, C22…
carbon steel : S235, A42 FP…
copper and alloys,
borated stainless.
MAIN WELDING PROCESSES





► Decontamination
EDF
61
room
► Fuel
storage basket
TIG,
Arc welding,
Semi-automatic, filled wire,
Semi-automatic, MIG and pulsed MIG,
Automatic, submerged arc.
62
FENOSOLTM
Rigid foam for filling,
impact absorption, fire
protection,
insulation and many other
applications.
► Shock
63
63
absorber
In partnership with the


FENOSOLTM is a rigid phenolic foam. It is
subject to continuous quality control under the
ISO 9001(2000 version) Quality System,
FENOSOLTM is used in the preparation of
special containers for the transport of
hazardous products for nuclear and defence
industry purposes. It provides good mechanical
protection and thermal insulation and is fire
resistant.
FENOSOLTM ADVANTAGES :
 Can be moulded or injected ; suitable for
creating complex shapes and for filling
largesized holes as well as small gaps,
 Available in a wide range of densities,
 Rigid, lightweight and strong,
 Very high mechanical strength in compression,
 Low, steady thermal conductivity makes for good
insulation,
 Excellent fire resistance (category M1 fire rating),
 Negligible emissions (category F1 fumes rating),
 CFC and HCFC free for protection of
environment.
Plastic
boilermaking
► Filtration
pilot
► Suction
DESIGN AND MANUFACTURE OF
COMPONENTS MADE OF :
 PVC,
 Polycarbonate,
 Perspex,
 Polypropylene,
 Polyethylene,
 Polyester resin,
 Corian.
hood AREVA
► Ventilation
► Perspex
64
box
gloves
► Corian
gloves box
► PVC
gloves box
► Polycarbonate
gloves box
shafts
Foundry
Machining of Lead





► Pieces
3 ICPE lead foundry : Genas, Marcoule, La
Hague,
2 ICPE allowed to cast lead from the nuclear
industry,
A capacity of several thousand tons per year,
Parts of a few kilograms to more than 20 tons,
An experience of more than 50 years in
techniques of lead implementations for the
nuclear industry.
of large size
► Shielding
65
on site
► Brick
► Machined
slab
► Pipework
protection
Dismantling
66
ROBATEL Industries offers its customers a
large range of dismantling services approved
by the CEA (CAEAR approval related to
studies, design and field work). Relying on its
significant experience feedback ROBATEL
Industries is in a position to display
unavoidable changes in studies, manufacture
and servicing.
Outline of
proposed
services




Maintenance and refurbishment of hot cells,
Annual maintenance contracts with AREVA
& CEA,
Loading of casks in pools and unloading,
Maintenance of casks :
regulatory maintenance of type B casks,
 repair of casks on site and in our workshops,
 tightness testing before transportation and assistance
to loading.







► Loading
casks (fuel rods)
on EDF plants
67
► Intervention
crane with mobile protection
Tightness testing and maintenance of glove
boxes,
Pipe testing,
Supply and assembly of biological
protections,
Installation of lock-chambers,
Management and disposal of radioactive
waste,
Supply of spare parts and assembly in
controlled area.
68