ANDES WP2: Uncertainties and covariances of nuclear data Arjan - - PowerPoint PPT Presentation

ANDES WP2: Uncertainties and covariances of nuclear data

Arjan Koning NRG ANDES semester meeting NEA Issy-les-Moulineaux November 19, 2010

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Contents

• Partner list
• Objectives
• Tasks
• Milestones and deliverables

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Objectives

Enhance the European capability to produce covariance data for isotopes important for advanced reactors Three aspects of nuclear data evaluation come together:

• Uncertainty/covariance evaluation of experimental data
• Uncertainty/covariance evaluation of data from models
• A proper theoretical treatment and evaluation of nuclear

reactions on actinides (especially fission models) and its relation with 1. and 2. In addition:

• Covariances for radioactive decay and fission yield data
• Use all of the above in processing, reactor and fuel cycle

codes. In ANDES-WP2, all this is organized in 5 tasks

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Partner list

• NRG (Koning): TALYS nuclear model code, production of nuclear

data libraries + covariances, RRR+URR+fast neutrons, applied (benchmarking) criticality, shielding and reactor calculations

• CEA-DAM (Bauge): experimental uncertainty methods + TALYS

fission model development

• CEA-CAD (de Saint-Jean): CONRAD resonance code
• Univ Bucharest(Sin): Fission modeling
• UNED/UPM (Cabellos): Uncertainty propagation for back-end of

the fuel cycle, apply covariance data in activation code.

• NNL (Mills): Covariances for fission yield and decay data, spent

fuel inventory and decay heat calculations

• TUW (Leeb): uncertainty methods: GENEUS
• CIEMAT (Gonzalez): fuel cycle codes
• JSI (Trkov): processing and application

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Task 2.1 : Scientific coordination

Task leader: NRG Monitoring of progress by all WP2 partners Collection of information for this meeting. For the rest, nothing specific since the kick-off meeting Several partners: new post-docs or PhD students in 2011

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Task 2.2:Covariance tool development

TASK leader: TU Wien

• Experimental covariance tool (CEA-DAM)
• Post-doc identified. She will start beginning 2011
• GENEUS evaluation tool (TU Wien):
• Activities started directly at 01-05-2010
• ANDES funds PhD student : Denise Neudecker
• Report of first results at JEFF meeting june 2010
• Uncertainties on OMP and level densities included
• Ongoing: extension of GENEUS (based on TALYS-

1.2) for fission channels

• CONRAD (CEA-DEN) evaluation tool
• Not yet started

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TU Wien (Leeb, Neudecker)

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Task 2.3 Covariance data evaluation

TASK leader: NRG NRG: covariance production for actinides:

• Extended nuclear data libraries with uncertainties for number of

fission neutrons (MF31) and fission neutron spectrum (MF35)

• Started new complete evaluation of Pu-239 including full

covariance data. Testing with Total Monte Carlo for WP3. Univ Bucharest: Improve methods for actinide evaluation:

• 2 weeks of EMPIRE development by Capote at JSI( Slovenia).
• Testing new models for direct and pre-equilibrium reactions.
• Uncertainties for n+237Np and n+242Pu assessed based on

different evaluations, experiments and EMPIRE-Kalman: will be used for Monte Carlo covariance evaluations.

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NRG (Koning, Rochman)

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TALYS code system

A loop over nuclear physics, data libraries, processing and applications:

• Resonance parameters + uncertainties
• An EXFOR database with more uncertainties than errors
• The TALYS code
• The Reference Input Parameter Library (RIPL)
• Software for remaining reaction types (nubar, fns + unc.)
• For many nuclides: A set of adjusted model parameters +

uncertainties + “non-physical evaluation actions”

• All major world libraries
• The ENDF-6 formatting code TEFAL
• NJOY, MCNP(X) + other codes
• A script that drives everything

The secret: Insist on absolute reproducibility

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Resonance Parameters .

TARES

Experimental data (EXFOR)

• Nucl. model

parameters

TALYS TEFAL

Output Output ENDF

• Gen. purpose

file ENDF/EAF

• Activ. file

NJOY

PROC. CODE

MCNP FIS- PACT Nuclear data scheme + covariances

• K-eff
• Neutron flux
• Etc.
• activation
• transmutation

Determ. code Other (ORIGEN) +Uncertainties +Uncertainties +Covariances +Covariances +Covariances +(Co)variances +Covariances +Covariances

TASMAN

Monte Carlo: 1000 TALYS runs

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TENDL: Complete ENDF-6 data libraries

MF1: description and average fission quantities MF2: resonance data MF3: cross sections MF4: angular distributions MF5: energy spectra MF6: double-differential spectra, particle yields and residual products MF8-10: isomeric cross sections and ratios MF12-15: gamma yields, spectra and angular distributions MF31: covariances of average fission quantities (TENDL-2010) MF32: covariances of resonance parameters MF33: covariances of cross sections MF34: covariances of angular distributions MF35: covariances of fission neutron spectra (TENDL-2010) and particle spectra (TENDL-2011) MF40: covariances of isomeric data (TENDL-2011)

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Resonance Parameters .

TARES

Experimental data (EXFOR)

• Nucl. model

parameters

TALYS TEFAL

Output Output ENDF

• Gen. purpose

file ENDF/EAF

• Activ. file

NJOY

PROC. CODE

MCNP FIS- PACT Nuclear data scheme: Total Monte Carlo

• K-eff
• Neutron flux
• Etc.
• activation
• transmutation

Determ. code Other codes +Uncertainties +Uncertainties +Covariances +Covariances

TASMAN

Monte Carlo: 1000 runs of all codes

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Optimization of Pu-239

• Select 120 ICSBEP benchmarks
• Create 630 random Pu-239 libraries, all within, or closely

around, the uncertainty bands

• Do a total of 120 x 630 =75600 MCNP criticality

calculations

• Do another 120 x 4 calculations:

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Optimization of Pu-239

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Optimization of Pu-239

• 6% of libraries have lower chi-2 than JEFF-3.1
• Library #307 has the lowest

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• Univ. Bucharest (Sin)

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UB: Cross sections of neutron induced reactions on 239Pu

• available evaluations: ENDF-VII, JEFF 3.1.1, JENDL 4,

ROSFOND 2010, TENDL 2009, JENDL/Ac, Minsk/Act, etc

• “very” preliminary calculations in the energy range 1 KeV-20 MeV

performed with EMPIRE-3 & RIPL-3

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Calculations with EMPIRE code

Direct - coupled channels ECIS06 Compound nucleus – Hauser-Feshbach, HRTW Preequilibrium – exciton model - PCROSS

Input parameters – default values from RIPL-3

 regional dispersive OMP for actinides (2408 for n, 5408 for p)  discrete level schemes (the recommended number of discrete levels adjusted)

 gamma strength functions MLO1(normalized to exp. strength function)

 level densities for normal states EGSM  fission barrier parameters (tuned to fit the experimental data)  level densities at saddles EGSM

Models

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(n,n’) (n,2n)

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In the next stage, most of the effort will be focused on direct and preequilibrium neutron emission.

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Task 2.4: Covariances for activation, decay and fission yields

Task leader: UPM NNL: Fission yield and decay data

• ACAB methods for these data investigated
• Method available for including each individual fissioning
• system. Correlations with decay data and time

dependence are being studied UPM: Covariance data for spent fuel inventories and decay heat:

• See presentation of Oscar Cabellos
• ANDES is combined with Spanish research and teaching

fellowship for a new student for ANDES: Carlos Javier Diez de la Obra.

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UNED (Sanz)

• System of reference: industrial-scale transmutation facility

EFIT

• core cooled by pure lead
• thermal power 400 MW,
• initial total mass of actinides 2.074 tonnes (21.7% MA)
• 150 GWd/tHM discharge burn-up corresponding to an

equilibrium cycle ( 778 irradiation days). 2011: Use Total Monte Carlo with ACAB code to get full uncertainties of inventories, using random ENDF-6 libraries and EAF (European Activation File) libraries.

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Task 2.5: Application to advanced reactors

Task leader: CIEMAT (Use covariance files in reactor and fuel cycle codes for designs from other EU projects. Determine uncertainty for most important parameters) No technical progress reported.

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Deliverables and milestones (year 1 only)

D2.1: Activation data libraries for Monte Carlo uncertainty propagation in fuel cycle code ACAB (M12)(NRG, CIEMAT, UPM)

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Conclusions

• WP2 on uncertainty data well underway
• New Phd and post-doc projects will start in 2011