Introduction to
IP Eurotrans - NUDATRA
Enrique M. González Romero
CIEMAT
IP-EUROTRANS Internal Training Course ITC2:
“Nuclear data for transmutation: status, needs and methods”
Santiago deCompostela, Spain
7/06/2006
Nuclear waste Partitioning and Transmutation (P&T)
Heterogeneity of Spent nuclear fuel Components
U + Activation wastes: Large volume and mass but low activity and heat.
FF:
5% of the mass but most of the radioactivity and heat at discharge.
Highly radioactive but of short live (30 years).
In particular Cs y Sr main heat source for the Geological repository at short term.
99Tc, 129I, 93Zr, ... long half-life (> 105 y) + soluble in repository (radiotoxicity concern)
LLFF:
Transuranic actinides: Pu + MA (Np, Am, Cm,...):
1.5% in mass but most of radiotoxicity and heat after 100 y. for more than 105 y.
Fissionable (proliferation and criticality concern) but can produce energy (Pu) !
P&T: Differentiated management for such heterogeneous components
5%
4,352%
Mass / U
4%
100,000%
100%
Mass / U
80%
3%
2%
1,003%
1%
0,062%
0,097%
0,002%
0%
60%
FF
Np
40%
24,960%
13,452%
20%
6,448%
4,352%
0,062%
1,003%
0,097%
0,002%
0%
Steel
O
Zr-al
U
FF
Np
Pu
Am
Cm
Pu
Am
Cm
U irrad
LWR (+FR)
Spent Fuel
PUREX
Pu irrad
Transmutation
Partitioning
FR or Surface Storage
Reactor prod.
Electricity
Am
Cm
Np
M.A. + F.F.
Advanced
Partitioning
LLFF
Cs / Sr
Inter. Storage
Otros
FF
Final Storage
Resid. Sec.
Transmutation
n + 239Pu (24000 y)  134Cs (2 y)+
104Ru
(stable) + 2 n + 200 MeV (energy)
n + 241Am (432 y)  242Am (16 h)
[capture]
242Am (16 h)  242Cm (163 d)
[b- decay]
242Cm (163 d)  238Pu (88 y) [a decay]
n + 238Pu (88 y)  142Ce (stable)+ 95Zr (64 d) + 2 n + 200 MeV (energy)
n + 99Tc (210000 y) 
100Tc
(16 s) + g.
n + 129I (15.700.000 y)  130I (12 h) + g.
100Tc
130I
(16 s) 
(12 h) 
100Ru
130Xe
(stable)
(stable)
[b-]
[b-]
Present in nuclear wastes
Medium Half-Life (<100 años)
Short Half-Life (< 30 dias)
High A actinides
Thermal and Fast Fission
Fast Fissión
Low Fission Cross Section
TRU Transmutation Scheme
Fast Spectrum
Fast Spectrum Transmutation Scheme
Av. Flux Intensity (n/cm2/s)
3,00E+15
Second
Hour
Day
Year
1 Time Unit
3600 31570560
86400
3E+07
Cm242
Cm243
Cm244
Cm245
Cm246
a / SF
a / EC/ SF
a / SF
a / SF
a / SF
a
100 / 6.2E-6
9 9 . 7 / 0 . 2 9 / 5 . 3 E- 9
100 / 1.35E-4
100 / 6.1E-7
100 / 3E-2
100
0,446
29,068
18,080
8490,695
4724,813
18,130
2,798
6,257
2,922
16,459
64,7%
8,0%
65,2%
11,4%
44,6%
Am241
Am242
Am242m
Am243
Am244
a / SF
b- / EC
IT / a / SF
a / SF
b- / EC
100 / 3.77E-10
82.7 / 17.3
9 9 . 5 / 0 . 4 6 / 1 E- 3
100 / 3.7E-9
100 / 4E-2
432,225
0,002
140,846
3,652
7361,922
17,792
1,844
4,892
44% : 44%
13,1%
8,4%
87,0%
Pu239
Pu240
Pu241
Pu242
Pu243
a / SF
a / SF
a / SF
b- / a
a / SF
b-
100 / 1.9E-7
100 / 3.1E-10
100 / 5.7E-6
100 / 2.45E-3
100 / 5.5E-4
100
87,644
24083,608
6556,805
14,334
372891,707
0,001
4,220
3,477
9,033
2,688
11,354
6,775
37,5%
19,4%
54,8%
14,2%
61,1%
30,6%
Np238
Np239
a / SF
b-
b-
100 / 2E-12
100
Pu239
a / SF
100
2137656,095
0,006
4,332
15,928
81,5%
13,1%
100 / 3.1E-10
0,006
15582935,494
0,001
Pu238
Np237
Cm247
Ln(2)/(sf)
24083,608
3,477
19,4%
Symbol & Mass
Decay modes
Branching ratios
Half-Life
Absorption-Half-Life
(n,g)/absoption
Framework and Strategy of P&T
Geological Disposal
Direct Disposal
Temporary Storage
for heat decay
Cs, Sr
Geological
Disposal
Spent Fuel
from LWRs
Partitioning
Stable FP, TRU losses
P&T
Pu, MA, LLFP
Stable FP, TRU losses
Transmutation
Dedicated Fuel
and
Dedicated Fuel and
LLFP target Fabrication
LLFP Target
Reprocessing
Pu, MA, LLFP
LLFP: Long lived fission products (Tc-99, I-129, Se-79, ...); MA: Minor Actinides (Am, Np, Cm)
Transmutation device requirements
Efficient
transmutation
 High (fast) neutron flux
 High burnup
 High Pu+MA and low U content
but very high safety standards
 Nuclear (Fast) Reactor
 Flexible
 Subcritical
ADS
The most efficient transmutation would be a reactor of significant power (nx100 or 1000 MW),
of fast neutron spectrum, with a fuel with very low Uranium content and high concentration of Pu
and MA.
A reactor with these characteristics shows an important lack of intrinsic safety:
Low delay neutron fraction
Small Doppler effect
Bad void coefficient
In addition the reactor needs a large operation flexibility, to be able to handle:
Very high burn-up levels in each irradiation cycle
Large reactivity evolution within one irradiation cycle
Very difficult for critical reactors and strong limitation on their transuranium elements load.
Two types of solutions:
A large number of fast reactors with small regions dedicated to transmutation (countries
with large park of nuclear power plants)
A small number of subcritical accelerator driven systems, ADS, dedicated to transmutation.
ADS = Accelerator Driven
Subcritical System
• Flexible enough to accept fuel with high
content on Pu and M.A.
• Low U content or pure Inert matrix to
optimize the transmutation performance
An ADS is a subcritical nuclear system (Keff =
0.95-0.98) whose power is sustained by a
external high intensity neutron source. Usualy
the neutrons are produced by spallation in heavy
nuclides (Pb) by high energy neutrons (~1 GeV)
Los aceleradores de mayor intensidad en energías
próximas a 1000 MeV
Acelerador del LANSCE de 800 MeV
en Los Alamos National Laboratory,
EEUU.
P&T will reduce the transuranic
actinide inventory, allowing:
• Reducing the radiotoxicity (1/100)
• Reducing the time to reach any
radiotoxicity level (1/100 – 1/1000)
• No proliferation risk in the repository
• Reducing HLW volume at repository
• Simplifying repository requirements
• Utilizing the Pu+MA energy



Reducing the radiotoxicity inventory and the volume of the High Level Wastes, HLW, of
future reactors and fuel cycles, to improve their sustainability
Increasing the capacity of the Geological Repository for the waste already produced, and
to be produced, by the present reactors
Facilitating the technical requirements and public acceptance of the Geological Repository
On the other hand P&T might:
· Increase the exposure risk of new fuel cycle plants (fabric., reproces., ADS) operators
· Increase the proliferation risk in the nuclear fuel cycle
· Increase the cost of nuclear energy production
R&D to optimize advantages limiting new risks and costs to acceptable limits!.
R&D for P&T: 5th Framework Program of UE
Nuclear Data and
Basic physics:
nTOF-ND-ADS
HINDAS
MUSE
Materials:
TECLA
SPIRE
MEGAPIE
ASCHLIM
Preliminary
Design:
PDS-XADS
Reprocessing:
PYROREP
PARTNEW
CALIXPART
Fuel:
Thorium Cycle
CONFIRM
FUTURE
Network: ADOPT
ADS Design Concepts of PDS-XADS
80MWth
Pb-Bi cooled XADS
50MWth
Pb-Bi cooled MYRRHA
80MWth
Gas-cooled XADS
0.00
Ansaldo
SCK·CEN
Framatome ANP
Development Scheme: FP5 to FP6
1999
2004
2005
FP6
2025
XT-ADS
Integrated Project on European Transmutation:
EUROTRANS
Steps towards a Demonstrator
Overall Objectives of EUROTRANS
 EUROTRANS aims to the demonstration of the technical feasibility
of transmutation using an ADS (3rd building block):
 Advanced design of an eXperimental facility demonstrating the
technical feasibility of Transmutation in an Accelerator Driven
System (XT-ADS), and conceptual design of the European
Facility for Industrial Transmutation (EFIT), DM1 DESIGN
 Provide validated experimental input from relevant coupling
experiments of accelerator / spallation target / sub-critical
blanket, DM2 ECATS
 Development and demonstration of the associated
technologies, especially fuels DM3 AFTRA, heavy liquid metal
technologies DM4 DEMETRA, and nuclear data DM5 NUDATRA,
 To prove its overall technical feasibility, and
 To carry out an economic assessment of the whole system.
Integrated Project EUROTRANS:
EUROpean Research Programme for the TRANSmutation of High
Level Nuclear Waste in an Accelerator Driven System (ADS)
 Partners: EUROTRANS integrates critical masses of resources and
activities, including education and training (E&T) efforts, of 45 participants
from 14 countries, being industry (10 participants), national research
centres (18), and 17 universities within ENEN.
 Overall budget: 23M€ EC contribution
Budget Share (EC Contribution)
 Duration: 4 years
75,00
50,00
25,00
JRC-EC
Universities
Research
Centres
0,00
Industry
EC Contribution in %
 Start date: April 2005
100,00
Structure of EUROTRANS
IP Co-ordinator
J.U. Knebel, FZK
EC
V. Bhatnagar
DM0 Management
Project Office
6.1M€
DM1 DESIGN
ETD Design
H. A. Abderrahim, SCKCEN
DM2 ECATS
Coupling
Experiments
5.5M€
G. Granget, CEA
DM3 AFTRA
Fuels
DM4 DEMETRA
HLM Technologies
DM5 NUDATRA
Nuclear Data
F. Delage, CEA
C. Fazio, FZK
E. Gonzalez, CIEMAT
3.3M€
5.3M€
1.1M€
Domain 1 DESIGN
Development of a detailed design of XT-ADS
and a conceptual design of the European
Facility for Industrial Transmutation EFIT
with heavy liquid metal cooling
DM1 DESIGN: Objectives
 To carry out a detailed design of an experimental ADS called XT-ADS
that construction can be started within the next 8 years.
 The XT-ADS should be as much as possible serving as a technological
test bench of the main components of an industrial scale
transmutation facility called EFIT
 To carry out a conceptual design of the industrial scale ADS Pb cooled
EFIT and a gas cooled back up option of EFIT
 To develop, construct and test the key components of the LINAC
technology that will be serving for XT-ADS as well as for EFIT. The
driving parameter in this work is the improvement of the beam
reliability
 To design the windowless spallation target module of the XT-ADS in
terms of thermo-mechanical, thermal-hydraulic and vacuum
 To reassess the global safety approach for ADS in presence of MA fuel
and apply it to the XT-ADS for assessment of DBC and DEC transients
for preparing the SAR for the XT-ADS
 To assess the investment and operational costs of the XT-ADS and
their scaling to EFIT and identify the needed R&D efforts
EUROTRANS: Design Domain
Domain DM1: DESIGN
Development of a reference DESIGN for the European Transmutation
Demonstrator (ETD) with heavy liquid metal cooling
 WP1.1 Reference Design Specifications
 WP1.2 Development and Assessment of Generic ETD and XTADS Designs
 WP1.3 High Power Proton Accelerator (HPPA) Development
 WP1.4 Spallation Target Proof of Feasibility
 WP1.5 Safety Assessment
 WP1.6 Cost Estimates and Planning Issues for the Reference
Design for the Generic ETD and XT-ADS
Preliminary Design Characteristics of the XTADS and EFIT Designs (1/2)
XT-ADS
EFIT
Design level
Advanced design
Conceptual design
Coolant
Pb-Bi
Pure Lead
Primary System
Integrated
Integrated
Power
50 to 100 MWth
≥ 300 MWth
Core Inlet Temp
300°C (350°C)
400°C
Core Outlet Temp
400°C (430°C)
480°C
Target Unit interface
Windowless
Windowless (backup:
window)
Target Unit geometry
Off-center
Centered
Fuel
MOX (accept for a MA Fuel)
(Pu, Am)O2 + MgO (or Mo)
Av. Fuel Power density
700 W/cm³
450 to 650 W/cm³
Fuel pin spacer
Grid
Grid
Fuel Assembly type
Wrapper
Wrapper / Wrapperless
Fuel Assembly cross
section
Hexagonal
Square (based on BREST
and PWR) or hexagonal
(FBR)
Preliminary Design Characteristics of the XTADS and EFIT Designs (2/2)
Fuel loading
Top / Bottom TBD
Top
Fuel monitoring
T and FF (per FA)
T and FF (per regions)
External fuel handling
RH oriented
TBD
Primary coolant
circulation in normal
operation
Forced with mechanical
pumps
Forced with mechanical
pumps
Primary coolant
circulation for DHR
Natural + Pony motor
Natural + Pony motor
Secondary coolant
Low pressure boiling water
Superheated water cycle
Reactor building
Below grade
Below grade (partially)
Seismic design
Mol Site seismic spectrum
Antiseismic supports
(horizontally)
Structural Material
T91 and A316L
TBD
Accelerator
LINAC (power: 2 ~ 5 MW)
LINAC (power: TBD)
Beam Ingress (1)
Top
Top
EFIT First « Remontage »
proposed by ANSALDO
Domain 2 ECATS
Experimental activities on the Coupling of an
Accelerator, a spallation Target and a Sub-critical
blanket
Special Situation: DM2 ECATS
Experimental activities on the Coupling of an Accelerator,
a spallation Target and a Sub-critical blanket
 The objective is to assist the design of XT-ADS and EFIT, provide
validated experimental input from relevant experiments at sufficient
power (20-100 kW) on the coupling of an accelerator, a spallation
target and a sub-critical blanket. The work programme will be specified
after the completion of a Feasibility Study.
 Expected outcome of the Feasibility Study:
 Description of required input for the design of XT-ADS and EFIT,
 Description of salient features of relevant coupling experiments,
 Summary of recommendations,
 Structured proposal of work programme.
 To perform ECATS requires collaboration with USA (RACE), Russian
Federation (SAD) and Belarussia (YALINA).
Input Data Base Validation Required for the
ADS Feasibility Study of DM2 ECATS
 Qualification of sub-criticality monitoring,
 Validation of generic dynamic behaviour of an ADS in a wide
range of sub-critical levels, sub-criticality safety margins and
thermal feedback effects,
 Validation of the core power / beam current relationship,
 Start-up and shut-down procedures, instrumentation
validation and specific dedicated experimentation,
 Interpretation and validation of experimental data,
benchmarking and code validation activities etc.,
 Safety and licensing issues of different component parts as
well as that of the integrated system as a whole.
Experiments within DM2 ECATS
 SAD Experiments (Russian Federation):
 Representative coupling of proton accelerator, spallation target
and fast subcritical core (k~0,95) at low power,
 Wide range of experiments, including shielding issues,
 Design of the facility to be consolidated soon,
 With appropriate funding, experiments could start in 2009.
 YALINA Facility (Belarus):
 Subcritical thermal neutron blanket with external source.
 RACE Experiments (USA) / GUINEVERE (Belgium)
Domain 3 AFTRA
Advanced Fuels for TRAnsmutation Systems
DM3 AFTRA: Nuclear Fuel Development
Objectives:
 Design, development and qualification in representative conditions
of a U-free fuel concept for the EFIT, compatible with the reference
design studied in DM1 DESIGN.
 Ranking of different fuel concepts according to their main out-ofpile properties, their in-pile behaviour and their predicted behaviour
in normal and transient operating conditions, and their safety
performance in accidental conditions.
 Recommendations about fuel design and fuel performance of the
most promising fuel candidate(s).
 Fuel selection:
 Reference fuel (selected from FP5 / FUTURE):
Oxide composite : (Pu, MA, Zr)O2 ; (Pu, MA)O2+MgO or Mo
 Backup solution (selected from FP5 / CONFIRM)
Nitride inert matrix fuel : (Pu, MA, Zr)N




WP3.1
WP3.2
WP3.3
WP3.4
TRU-fuel Pre-design and Performance Assessment
TRU-fuel Safety Assessment
Irradiation Tests and Fuel Qualification
Out-of-pile Property Measurements
DM3 AFTRA: Status
Status of WP3.1: TRU-fuel pre-design and performance assessment
 Difficulties to select the best fuel candidate!
 Very limited knowledge:
 Experimental work remains difficult (poor availability of the facilities +
overbooking)
 PIE results are rare (especially on Mo)
 Choice is premature
 The ADS fuel reprocessability has never been studied
 EUROPART does not address the ADS fuel reprocessing !
 MgO-fuel, ranked higher in FUTURE, is recently suspected to be not
stable enough under irradiation/temperature (volatilization risk)
 Mo-fuel is proposed as the new reference for EUROTRANS
 But large uncertainties on the behaviour of Mo under irradiation
 Transmutation capability significantly reduced
 Enrichment in 92Mo required
 Irradiations foreseen
 FUTURIX-FTA in Phénix (irradiation of U-free fuels repr. of EFIT fuels)
 HELIOS in HFR (irradiation of Am-bearing IMF/instrumented pins)
 BODEX in HFR (irradiation of inert matrix doped with 10B)
Domain 4 DEMETRA
DEvelopment and assessment of structural
materials and heavy liquid MEtal technologies for
TRAnsmutation systems
DM4 DEMETRA: Objectives
 Improvement and assessment of the Heavy Liquid Metal (HLM)
technologies and thermal-hydraulics for application in ADS, and in
particular to EFIT and XT-ADS, where the HLM is both the spallation
material and the primary coolant.
 Characterisation of the reference structural materials in
representative conditions (with and without irradiation environment)
in order to provide the data base needed for design purposes, e.g.
fuel
cladding,
in-vessel
components,
primary
vessel,
instrumentation, spallation target with or without beam window.
 Challenges:
Irradiation experiments in HLM
Large scale thermal-hydraulics tests (still to be defined)
Long-term corrosion tests and mechanical tests in HLM
Free surface characterisation
Summary of the MEGAPIE experiment
DM4 DEMETRA: Test Facilities
 In FP5, a
complementary
combination of
test facilities was
set up in
Europe.
 EUROTRANS is
fully using these
test facilities.
CorrWett Loop
PSI
STELLA Loop
CEA
CIRCE Loop
ENEA
VICE Loop
SCK-CEN
CHEOPE Loop
ENEA
TALL Loop
KTH
CIRCO Loop
CIEMAT
DM4 DEMETRA: Activities
 WP4.1 Specification and Fabricability of the Reference Materials
and its Operation Conditions
 WP4.2 Reference Materials
technology development
Characterisation
in
HLM
and
 WP4.3 Reference Materials Irradiation Studies
 WP4.4 Advanced
Techniques
Thermal-hydraulics
 WP4.5 Large-scale Integral Tests
 WP4.6 MEGAPIE Related Studies: PTA
and
Measurement
Domain 5 NUDATRA
NUclear DAta for TRAnsmutation
Nuclear data for Transmutation from the fuel cycle point of view
The isotopic composition of the equilibrium fuel, and correspondingly of the losses finally
going to the storage, is defined by:
 The isotopic composition of the LWR wastes feed into the transmutation reactor
 the isotopes decay constants,
 the neutron flux intensity (reactor power) and,
 the effective cross sections of the activation reactions
Activation reaction Cross section
(n,g), (n,g)* of actinides with
(n,2n) +… half-live > 100d

Neutron flux Spectrum
elastic, inelastic,(n,2n),…
fuel matrix, Struct. Materials, coolant
Transmutation takes place in a reactor: Critical or Subcritical (ADS)
Critical Reactors or ADS devoted to transmutation present new features:
In all cases
New fuels: High content on minor actinide and high mass Pu isotopes
Well adapted to Advanced reprocessing.
Very high Burn-up per irradiation cycle.
Most Frequently
Fast neutron flux spectrum.
Final objective: Long term radiotoxicity reduction
Subcritical configurations + Spallation sources
New Technologies: Coolant: Molten Lead or Pb/Bi,
Fuel matrix: Inert matrix, Th matrix, ..
New isotopic composition of transmutation fuels
Contributions to capture of present and transmutation fuels
Contributions to fission of present and transmutation fuels
Integrated reaction capture and fission reaction rate versus energy
in a FAST neutron energy spectrum
Nuclear data uncertaities final consecuences
Criteria for the Sensitivity Analysis:
Focusing the nuclear data on its final P&T application
The FP5 guidelines for measurement priorities: direct contributions to the reaction rates, availability of the
samples, and differences observed between different nuclear data bases.
This simple sensitivity analysis has proven its merits within the nTOF-ADS program by indicating the isotope,
reaction and required accuracy and served to reduce unnecessary efforts.
However a full systematic sensitivity analysis is missing and has been requested both in the
meetings of the BASTRA cluster and in the WPPT of the NEA/OCDE.
Only this systematic sensitivity analysis can provide precise scientific arguments to properly
define the impact of the data uncertainty and the priority of needs for new measurements.
This sensitivity analysis have to evaluate the impact of the uncertainties of the nuclear data on:
• the performance (power and operability),
• safety (dynamic parameters, shielding, radioprotection, ...) and
• cost (power, shielding, ...) of
- the transmutation device (ADS and critical reactors) and
- the final inventory of the repository depending on the nuclear cycle options.
Parameters for the sensitivity analysis
Any detailed engineering design of a transmutation device or of fuel cycle will have to
manage the consequences of the nuclear and other technical data uncertainties.
However whereas some corrections (like the power level of an ADS) are easy to handle
(beam intensity adjustment), others affect the viability or final result of the concept or may
have large economical impact.
The sensitivity analysis has to be concentrated on the effect of the nuclear data uncertainties
on these second type of parameters. Some important parameters:
Keff :
(rather than n-multiplication)
a) At construction -> overdesign of fuel and control system
b) Evolution with burn-up must be predictable
Dynamic parameters: beff, neutron lifetime, Doppler effect, Reactivity coefficients,...
Critical transmuters, ADS in abnormal conditions, Evolution with burn-up, Reactivity control.
Shielding requirements: Related with the small part of the very energetic spallation neutrons.
Material damage: In particular in the window, gas releasing reactions.
The fuel cycle: Equilibrium composition of multiply-recycled fuels in closed fuel cycles.
The composition and amount of the different spent fuels and of the final disposal:
Activation of the fuel, coolant, structures, accelerator,... + the fission & spallation products.
The spallation source performance: Production and transport of high energy neutrons, f*.
DM5 NUclear DAta for TRAnsmutation: Objectives
CEA (France), CIEMAT (Spain), CNRS (France), CSIC (Spain), FZJ (Germany), FZK (Germany), GSI
(Germany), INFN (Italy), INRNE (Bulgaria), NRG (Netherlands), PSI (Switzerland), SCK-CEN
(Belgium), JRC-Geel (EC), Universities: AGH (Poland),TUW (Austria), KTH (Sweden), ULG (Belgium),
UNED (Spain), USDC (Spain), USE (Spain), UU (Sweden), ZSR (Germany).
 Improvement and assessment of the simulation tools and associated
uncertainties for ADS transmuter core, its shielding and associated fuel cycle.
 The activity is essentially focussed on the evaluated nuclear data libraries and
reaction models for materials in transmutation fuels, coolants, spallation targets,
internal structures, and reactor and accelerator shielding, relevant for the design
and optimisation of the Generic ETD and XT-ADS.
NUDATRA Workpackages
 WP5.1 Sensitivity Analysis and Validation of Nuclear Data and
Simulation Tools
 WP5.2
Low and Intermediate Energy Nuclear Data Measurements
 WP5.3 Nuclear Data Libraries Evaluation
Energy Models
 WP5.4
and
High Energy Experiments and Modelling
Low-intermediate
NUDATRA Activities Concentrate on 4 Topics
 Pb-Bi cross sections: inelastic, (n,xn), Po production (B.R.)
 MA: Capture in 243Am + Fission on 244Cm
 High energy codes improvement and measurements:
Absolute Spallation product x-section, Gas and Light Charged
Particles production
 Sensitivity analysis of ETD fuel cycle
 These topics are addressed from the different aspects
required to be used on the ETDs analysis and design:
Measurements, Evaluation, Integration on standard tools,
Validation and Sensitivity analysis.
Uncertainties propagation and Sensitivity analysis
Basis for a quantitative assessment of the nuclear data precision requirements
For the transmutation reactor:
Some although still few and generic analysis of ADS parameters sensitivity
analysis available.
A specific study will be performed within the EUROTRANS DM1 Design
activities for the XT-ADS and the Generic-ETD.
For the the fuel cycle and the repository parameters:
Very few analysis available.
Specific methodologies required
Differential sensitivity coefficient determination
Combination of random sampling of deviations
Topics
Transmutation performance
Fuel characteristics at reprocessing, fabrication and repository
Isotopic composition of the transmutation plant fuel at equilibrium (in
multi-recycling scenarios)
Data for Actinides, FF and Activation products are concerned
Cross sections, Branching ratios, FF yields, Decay properties
MC and Deterministic codes: EVOLCODE or KAPROS/KARBUS
Low and intermediate energy nuclear data measurements:
Pb and Bi cross section and branching ratios
High resolution excitation functions for the inelastic
scattering cross sections of Pb and Bi
Critical to model correctly the ADS core neutron spectra
and 209Bi, thr-20 MeV by (n,n’g) at Gelina
Gamma-ray production cross sections are
measured and total and level inelastic cross
sections will be deduced
206, 207, 208Pb
Bi capture branching ratio
Production of 210gBi is the mechanism leading to 210Po
production. 210mBi decay a to 206Tl.
210Po is one of the main ADS target and coolant activation
concerns
209Bi(n,g)210m,gBi
capture B.R. and energy dependence
The time-of-flight technique will be used at Gelina
Two HPGe detectors will be used to distinguish
between capture events leading to the ground
state and the meta-stable state
Compensation for g angular dependence
Gelina @ Geel (UE)
Low and intermediate energy nuclear data measurements:
Pb and Bi cross section and branching ratios
Measurements of Pb (n,xn’ ) cross section at 100 MeV
Non existing data required for Pb based ADS high energy
neutron shielding calculations and spallation n multiplication
Pb (n,xn’) at Uppsala
The Scandal facility will be used at the neutron
beam facility of The Svedberg Laboratory
Measurements of Pb and Bi (n,xn) cross sections
Effects on the neutron multiplication and the source importance
of ADS cooled with Pb/Bi or using Pb/Bi spallation target
206Pb,209Bi
(n,xng)
Online HPGe detectors at Gelina, Uppsala? nTOF?
Basic feasibility of the method demonstrated in FP5
Gelina @ Geel
(UE-Belgium)
Cyclotron @ Uppsala (Sweden)
Low and intermediate energy nuclear data measurements:
MA Capture and Fission cross sections
Neutron capture cross section of MA.
Better data required for Transmutation of MA.
243Am is the path to 244,245,246,247Cm production
243Am
(n,g) at nTOF-Ph2 (CERN)
From 0.1 eV -1 MeV
Time of flight + 4p TAC.
The methodology and setup tested in
2004 at the FP5 nTOF-ADS project.
New special target
Neutron 244Cm fission cross section
Extremely difficult direct measurement (Short
half-life 18.1y and high spontaneous fission)
244Cm Elimination in ADS and fission model
244Cm(n,f)
from 243Am(3He,pf)
Measurements of the transfer
reactions 243Am(3He,pf) at Orsay +
Evaluations and models for the
formation of the composite nucleus
nTOF @ CERN
TAC g calorimeter
Nuclear data libraries evaluation and low-intermediate
energy models
Measurements must be evaluated to become useful for simulations
Improvement of low and intermediate energy reaction models
Nuclear model code TALYS
Methods to generate covariance data
Evaluation of new MA data (results available from nTOF)
Optical model, pre-equilibrium, compound nucleus and fission model
parameters will be fine-tuned
Priority to Americium isotopes in the fast neutron range
The resonance regions will also be analyzed
Re-evaluation of data libraries for Pb and Bi
Using the data from the WP5.2 to complement the existing and FP5 data
(nTOF, IRMM…)
High energy experiments and modeling
The energy range (200-1000 MeV) specific of the ADS spallation target
Completing the experimental database of the HINDAS FP5 project
(Very big progress on H.E. models but still some weak points)
High energy experiments for Radioactivity, chemical
modification and damage assessment
Total fission cross-section as a function of E between
200 MeV and 1 GeV for Pb and W
Production of long lived Intermediate mass fragments
as 7Be and 10Be from Bi, W, Ni targets: 100-1000 MeV
Helium production in W or Ta and Fe or Ni, between
E=100-800 MeV (NESSI/PISA experiment at FZJ)
GSI @ Darmstadt
(Germany)
High energy experiments and modeling
The energy range (200-1000 MeV) specific of the ADS spallation target
High energy Nuclear model improvement
Extension of INCL4 to low energies and composite Light Charged Particle
(LCP) production
Improvement of ABLA:
Fission,
Composite LCP
Intermediate Mass Fragments
Quality assessment, validation and impact of the new models in ETD
simulations
Implementation in High Energy transport codes (MCNPX, …)
Calculations of radiotoxicity, radioactivity due to residue production in the
MEGAPIE
Calculations of DPA, chemical composition modifications, and activities in
ETD with the new codes
Improvement of Transmutation plants simulation programs
and Validation of Data, Models and programs
The final goal for applications is to improve precision on simulations
Simulation programs that will be developed:
MCB, EVOLCODE and maybe KAPROS/KARBUS.
Validation Nuclear data and models for the spallation target:
Residual nuclei production in SINQ targets.
Measurements of absolute activities of residues (eg.: 194Hg, 207Bi) in
spallation target models (Dubna, PSI).
Minor actinide and Pb nuclear data validation in integral experiments
Fission cross section from MASURCA (Cadarache) experiments
240,241,242Pu, 237Np and 241,243Am
Other Minor actinide and Pb nuclear data validation based on results from
ISTC projects
Facilities:
BFS, SAD, Yalina
Experiments completed and in preparation
GSI @ Darmstadt
(Germany)
Gelina @ Geel (UEBelgium)
Cyclotron @ Uppsala
(Sweden)
nTOF @ CERN
(Switzerland)
and its TAS g-calorimeter
Neutron capture (n,g)
resonances in one actinide