Introduction toIP Eurotrans - NUDATRA

Enrique M. González RomeroCIEMAT

7/06/2006

IP-EUROTRANS Internal Training Course ITC2:

“Nuclear data for transmutation: status, needs and methods”

Santiago deCompostela, Spain

Nuclear waste Partitioning and Transmutation (P&T)

6,448%

13,452%

24,960%

100,000%

4,352%0,062%

1,003% 0,097% 0,002%

0%

20%

40%

60%

80%

100%

Mas

s /

U

Steel O Zr-al U FF Np Pu Am Cm

4,352%

0,062%

1,003%

0,097% 0,002%

0%

1%

2%

3%

4%

5%

Ma

ss

/ U

FF Np Pu Am Cm

Heterogeneity of Spent nuclear fuel ComponentsU + 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.

LLFF: 99Tc, 129I, 93Zr, ... long half-life (> 105 y) + soluble in repository (radiotoxicity concern)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

Partitioning

LWR (+FR) Spent Fuel PUREX

U irrad

Pu irrad

M.A. + F.F.

Am

Resid. Sec.

Cm

Np

Cs / Sr

LLFF

Otros FF

Tra

nsm

utat

ion

Inter. Storage

Final Storage

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) [- decay]

242Cm (163 d) 238Pu (88 y) [ decay]

n + 238Pu (88 y) 142Ce (stable)+ 95Zr (64 d) + 2 n + 200 MeV (energy)

Transmutation

AdvancedPartitioning

FR or Surface Storage

Reactor prod. Electricity

n + 99Tc (210000 y) 100Tc (16 s) + . 100Tc (16 s) 100Ru (stable) [-]

n + 129I (15.700.000 y) 130I (12 h) + . 130I (12 h) 130Xe (stable) [-]

Fast Spectrum Transmutation Scheme

Present in nuclear wastes Thermal and Fast FissionMedium Half-Life (<100 años) Fast FissiónShort Half-Life (< 30 dias) Low Fission Cross SectionHigh A actinides

Av. Flux Intensity (n/cm2/s)3,00E+15

Cm242 Cm243 Cm244 Cm245 Cm246 Cm247Second 1 Time Unit / SF / EC/ SF / SF / SF / SF

Hour 3600 31570560 100 / 6.2E-6 99.7/0.29/ 5.3E- 9 100 / 1.35E-4 100 / 6.1E-7 100 / 3E-2 100

Day 86400 0,446 29,068 18,080 8490,695 4724,813 15582935,494

Year 3E+07 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 / SF /EC IT / / SF / SF / EC

100 / 3.77E-10 82.7 / 17.3 99.5/0.46/1E- 3 100 / 3.7E-9 100 / 4E-2

432,225 0,002 140,846 7361,922 0,001

3,652 17,792 1,844 4,892

44% : 44% 13,1% 8,4% 87,0%

Pu238 Pu239 Pu240 Pu241 Pu242 Pu243 / SF / SF / SF / / SF

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%

Np237 Np238 Np239 Pu239 Symbol & Mass / SF / SF Decay modes

100 / 2E-12 100 100 100 / 3.1E-10 Branching ratios2137656,095 0,006 0,006 24083,608 Half-Life

4,332 15,928 3,477 Absorption-Half-Life81,5% 13,1% 19,4% (n,)/absoption

TRU Transmutation SchemeFast Spectrum

Ln(2)/()

Framework and Strategy of P&TGeological Disposal

Dedicated Fuel andLLFP target Fabrication

Pu, MA, LLFP

Direct Disposal

P & T

PartitioningSpent Fuelfrom LWRs

Transmutation

GeologicalDisposal

Dedicated Fueland

LLFP TargetReprocessing

Stable FP, TRU losses

Pu, MA, LLFP

Stable FP, TRU losses

Cs, Sr Temporary Storagefor heat decay

LLFP: Long lived fission products (Tc-99, I-129, Se-79, ...); MA: Minor Actinides (Am, Np, Cm)

Geological DisposalGeological Disposal

Dedicated Fuel andLLFP target Fabrication

Pu, MA, LLFP

Dedicated Fuel andLLFP target Fabrication

Pu, MA, LLFP

Direct Disposal

P & T

PartitioningSpent Fuelfrom LWRs

Transmutation

GeologicalDisposal

Dedicated Fueland

LLFP TargetReprocessing

Stable FP, TRU losses

Pu, MA, LLFP

Stable FP, TRU losses

Cs, Sr Temporary Storagefor heat decay

LLFP: Long lived fission products (Tc-99, I-129, Se-79, ...); MA: Minor Actinides (Am, Np, Cm)

Efficient High (fast) neutron flux Nuclear (Fast) Reactortransmutation High burnup Flexible

High Pu+MA and low U content Subcritical but very high safety standards

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 fractionSmall Doppler effectBad void coefficient

In addition the reactor needs a large operation flexibility, to be able to handle:Very high burn-up levels in each irradiation cycleLarge 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.

Transmutation device requirements

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

ADS = Accelerator Driven System

también conocido como ADSS = Accelerator Driven Subcritical System

Un ADS es un conjunto nuclear multiplicativo subcrítico cuya operación está mantenidapor un acelerador de protones que genera una fuente externa de neutrones en unblanco de esplación.

protones

Aceleradorde

partículas

Blanco deespalación

Conjunto nuclearsubcrítico

neutrones

Fisiones

Barras con los residuos (actínidos)actuando como combustible

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 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!.

• 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

R&D for P&T: 5th Framework Program of UE

Nuclear Data and Basic physics:nTOF-ND-ADS

HINDASMUSE

Materials:TECLASPIRE

MEGAPIEASCHLIM

Fuel:Thorium Cycle

CONFIRMFUTURE

Reprocessing:PYROREPPARTNEW

CALIXPART

Preliminary Design:

PDS-XADS

Network: ADOPT

ADS Design Concepts of PDS-XADS

0 . 0 0

80MWth Pb-Bi cooled XADS

Ansaldo

80MWth Gas-cooled XADS

Framatome ANP

50MWth Pb-Bi cooled MYRRHA

SCK·CEN

Development Scheme: FP5 to FP6

1999

2004

2005

2025

XADS (Gas)

80 MW(th)

250 W/cm

single batch loading

MYRRHA (Pb-Bi)

50 MW(th)

500 W/cm

multi batch loading

FP5

XADS (Pb-Bi)

80 MW(th)

110 W/cm

single batch loading

FP6

XADSDemonstration of technological

feasibility of

an ADS system

XT-ADSShort-term demonstration

of transmutation on a sizable scale

and of the ADS behaviour

Generic ETDLong-term

transmutation on an

industrial scale

FP ObjectivesDesign Concepts

Generic ETD

Several 100 MW(th)

250 - 300 W/cm

multi batch loading

European Transmutation Demonstration

advanced design

preliminary design, economics,

scalability to EFIT

ETD / XT-ADS

< 100 MW(th)

250 - 300 W/cm

multi batch loading

XADS (Gas)

80 MW(th)

250 W/cm

single batch loading

MYRRHA (Pb-Bi)

50 MW(th)

500 W/cm

multi batch loading

FP5

XADS (Pb-Bi)

80 MW(th)

110 W/cm

single batch loading

FP6

XADSDemonstration of technological

feasibility of

an ADS system

XT-ADSShort-term demonstration

of transmutation on a sizable scale

and of the ADS behaviour

Generic ETDLong-term

transmutation on an

industrial scale

FP ObjectivesDesign Concepts

Generic ETD

Several 100 MW(th)

250 - 300 W/cm

multi batch loading

European Transmutation Demonstration

advanced design

preliminary design, economics,

scalability to EFIT

ETD / XT-ADS

< 100 MW(th)

250 - 300 W/cm

multi batch loading

Generic ETD

Several 100 MW(th)

250 - 300 W/cm

multi batch loading

European Transmutation Demonstration

advanced design

preliminary design, economics,

scalability to EFIT

ETD / XT-ADS

< 100 MW(th)

250 - 300 W/cm

multi batch loading

FP6 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

Duration: 4 years

Start date: April 2005

Structure of EUROTRANS

DM2 ECATSCoupling

ExperimentsG. Granget, CEA

DM4 DEMETRAHLM Technologies

C. Fazio, FZK

DM1 DESIGNETD Design

H. A. Abderrahim, SCK-CEN

DM5 NUDATRANuclear Data

E. Gonzalez, CIEMAT

DM3 AFTRAFuels

F. Delage, CEA

IP Co-ordinatorJ.U. Knebel, FZK

DM0 ManagementProject Office

ECV. Bhatnagar

6.1M€ 5.5M€

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

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 XT- ADS 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

EUROTRANS: Design Domain

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 XT-ADS and EFIT Designs (1/2)

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

Preliminary Design Characteristics of the XT-ADS and EFIT Designs (2/2)

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

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).

Experimental activities on the Coupling of an Accelerator, a spallation Target and a Sub-critical blanket

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

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-of-pile 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

DM3 AFTRA: Nuclear Fuel Development

WP3.1 TRU-fuel Pre-design and Performance Assessment WP3.2 TRU-fuel Safety Assessment WP3.3 Irradiation Tests and Fuel Qualification WP3.4 Out-of-pile Property Measurements

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)

DM3 AFTRA: Status

Domain 4 DEMETRA

DEvelopment and assessment of structural materials and heavy liquid MEtal technologies for

TRAnsmutation systems

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 HLMLarge scale thermal-hydraulics tests (still to be defined) Long-term corrosion tests and mechanical tests in HLM Free surface characterisationSummary of the MEGAPIE experiment

DM4 DEMETRA: Objectives

DM4 DEMETRA: Test Facilities

In FP5, a complementary combination of test facilities was set up in Europe.

EUROTRANS is

fully using these test facilities.

STELLA LoopCEA

CIRCE LoopENEA

TALL LoopKTH

CIRCO LoopCIEMAT

CorrWett LoopPSI

VICE LoopSCK-CEN

CHEOPE LoopENEA

WP4.1 Specification and Fabricability of the Reference Materials and its Operation Conditions

WP4.2 Reference Materials Characterisation in HLM and technology development

WP4.3 Reference Materials Irradiation Studies

WP4.4 Advanced Thermal-hydraulics and Measurement Techniques

WP4.5 Large-scale Integral Tests

WP4.6 MEGAPIE Related Studies: PTA

DM4 DEMETRA: Activities

Domain 5 NUDATRA

NUclear DAta for TRAnsmutation

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 Neutron flux Spectrum(n,), (n,)* of actinides with elastic, inelastic,(n,2n),…(n,2n) +… half-live > 100d fuel matrix, Struct. Materials, coolant

Nuclear data for Transmutation from the fuel cycle point of view

Transmutation takes place in a reactor: Critical or Subcritical (ADS)

Critical Reactors or ADS devoted to transmutation present new features:

In all casesNew fuels: High content on minor actinide and high mass Pu isotopes

Well adapted to Advanced reprocessing.

Very high Burn-up per irradiation cycle.

Most FrequentlyFast 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 energyin a FAST neutron energy spectrum

Nuclear data uncertaities final consecuencesCriteria 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 : a) At construction -> overdesign of fuel and control system(rather than n-multiplication) b) Evolution with burn-up must be predictable

Dynamic parameters: eff, 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, *.

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.

DM5 NUclear DAta for TRAnsmutation: Objectives

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 and Low-intermediate Energy Models

WP5.4 High Energy Experiments and Modelling

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 analysisBasis 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

TopicsTransmutation 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 BiCritical to model correctly the ADS core neutron spectra 206, 207, 208Pb and 209Bi, thr-20 MeV by (n,n’) at Gelina

Gamma-ray production cross sections are measured and total and level inelastic cross sections will be deduced

Bi capture branching ratioProduction of 210gBi is the mechanism leading to 210Po production. 210mBi decay to 206Tl.210Po is one of the main ADS target and coolant activation concerns 209Bi(n,)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 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 multiplicationPb (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,xn)

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 production243Am (n,) at nTOF-Ph2 (CERN)

From 0.1 eV -1 MeV

Time of flight + 4 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 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 modelingThe energy range (200-1000 MeV) specific of the ADS spallation targetCompleting 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 modelingThe 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 LCPIntermediate 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 programsThe 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 experimentsFission 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

Gelina @ Geel (UE-Belgium)

GSI @ Darmstadt (Germany)

Cyclotron @ Uppsala (Sweden)

nTOF @ CERN (Switzerland)and its TAS -calorimeter

Neutron capture (n,) resonances in one actinide