Experimental Data Required for Code and Data Validation and for Use in Training for Radiation Transp

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Experimental Data Required for Code and Data
Validation and for Use in Training for Radiation
Transport and Damage Analyses

• Enrico Sartori OECD/NEA Data Bank

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Outline

• Components / research items
• damage mechanism, response to radiation
• radiation field, fluence
• uncertainties (experimental, calculational)
• Knowledge preservation
• basic data
• data from integral experiments
• measurement techniques
• microscopic radiation damage codes
• radiation transport codes

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(No Transcript)
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Todays codes for damage mechanism

• MARLOWE 15A, Computer Simulation of Atomic
  Collisions in Crystalline Solids
• SPECTER-ANL, Neutron Damage for Material
  Irradiation
• SRIM-2003, Stopping Power and Range of Ions in
  Matter
• UNF, Multistep Compound Nucleus Neutron
  Cross-Sections and Spectra for Structural
  Materials
• RICE, Energy Exchange Matrix, Damage
  Cross-Sections, Recoil Energy Spectra
• NJOY/HEATR Generates heat production cross
  sections (KERMA factors) and radiation-damage-ener
  gy production cross
• MACK, Fluence to Kerma Generator
• KAOS-V, Neutron Fluence to Kerma Factor
  Evaluation
• LSL-M2, Neutron Spectra Log Adjustment for
  Dosimetry Applications

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Todays codes / models

• Displacements per atom (DPA), displacement rates
• primary knock-on atom (PKA) spectra, or primary
  recoil spectra
• kinetic energy release in material (Kerma), or
  damage energy, heat production cross sections,
  Fluence to Kerma
• gas-production rates
• for threshold fluence, DPA, PKA improvements in
  translating the knowledge of flux/fluence to
  knowledge of the degree of metal structure
  degradation are needed
• for this, basic physics models of metal damage
  phenomena during irradiations of components are
  required

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Models for the future ?

• Efforts are being placed into material research
  using
• Molecular dynamics
• ab-initio methods - based on first principles
• The objective is the design of improved
  materials, better withstanding radiation damage.
  However these models give today only qualitative
  answers. Much further work is required to get
  reliable quantitative results.
• In the longer term
• Integrated multi-scale numerical modelling of
  nuclear materials

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(some) data for radiation damage

• ZZ KERMAL, Neutron and Gamma Kerma Library
• ZZ RECOIL/B, Heavy Charged Particle Recoil
  Spectra Library for Radiation Damage Calculation
• ZZ DAMSIG84, 640-Group Damage Cross-Section
  Library
• ZZ SNLRML, Dosimetry Cross-Section
  Recommendations
• ZZ VITAMIN-J/KERMA, Gas Production
  Cross-Sections, Neutron and Gamma Kerma
• ZZ DLC-10B AVKER, Neutron Kerma Response Function
  Data Library
• ZZ KAOS/LIB-V, Kerma Factors, Nuclear Response
  Function Library for Fission, Fusion

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Characterisation of radiation field / flux /
fluence

• Characterisation of source
• characterising fuel assemblies, position
  relative to structures, materials
• core flux calculation
• power history
• For this we need
• Codes for
• radiation transport,
• in-core fuel management,
• isotope burnup / depletion, build-up
• Basic Nuclear Data
• cross-sections
• nuclear decay data
• dosimetry response functions
• System / integral data from experiments
• reactor physics
• radiation shielding

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What is already being taken care of

• Basic nuclear data
• experiments (CINDA, EXFOR)
• evaluations (JEFF, ENDF/B, JENDL)
• Radiation Transport / Burnup codes
• applies to many other fields besides material
  damage
• institutional centres NEA Data Bank (EC is a
  member)

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Where efforts are badly needed (1/2)

• Integral / system experiment data to validate
  codes and basic data used for predicting
  flux/fluence
• Without such data, no confidence in the methods
  can be built. We need to check it against data
  from real systems (as compared to virtual)
• Many expensive high-quality experiments have been
  carried out but the data is often stored in dusty
  reports on archive shelves of dismantled
  facilities
• New facilities are unlikely to be built these
  experiments will not be repeated

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Where efforts are badly needed (2/2)

• Refined radiation damage models and codes -
  suitable for predicting behaviour in new
  materials
• PWR fuel UO2, (UPu)O2, cladding Zr-alloys,
  internals austenitic steels, PV tempered
  bainitic steel
• HTR fuel UO2, (UPu)O2,particle coating
  pyrolitic C, SiC, ZrCmoderator C (graphite)
• FGCR fuel (UPu)C / (UPu)Ninert microscopic
  grains TiC, ZrC, TiN, ZrNstructural materials
  Nb1Zr, SiC
• Multi-scale numerical modelling/validation will
  be an important research theme for the future

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Integral Experiments (1/3)

• Crucial issues of Reactor Physics, Shielding -
  Radiation Damage, Criticality Safety, Fuel
  Behaviour, Thermal-hydraulics etc. for Reactor
  and Fuel Cycle installation design
• Assessment of calculational tools
• Validation of nuclear data performance
• Model validation / improvement of predictive
  power
• Developing an approach of global method and data
  validation, using integral experiments

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Integral Experiments (2/3)

• Radiation Shielding / Transport / Source
  characterisation SINBAD
• reactor shields
• reactor pressure vessel
• different materials
• different spectra / parameters reactors , fusion
  blanket, accelerators
• Reactor Physics Validation of source/ flux /
  fluence prediction IRPhE
• LWR, HWR, HTR, FR, ADS, etc.

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SINBAD - Radiation Shielding Experiments -
Methods

• This unique set of experiments is stored in a
  standard, computer readable format, following
  peer review and quality assurance principles. It
  is disseminated to the user community for
  qualification of their application software and
  data by the RSICC and the NEA Data Bank.
• SINBAD data include benchmark information on
• (1) the experimental facility and the source
• (2) the benchmark geometry and material
  composition and
• (3) the detection system, measured data, and an
  error analysis.
• A full reference section is included with the
  data. Relevant graphical information, such as
  experimental geometry or spectral data, is
  included.
• All information that is compiled for inclusion
  with SINBAD has been verified for accuracy and
  reviewed by two scientists.
• The set of primary documents used for the
  benchmark compilation and evaluation are provided
  in computer readable form.

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By Application

• reactor shielding, pressure vessel dosimetry
• completed (32)
• do be compiled / evaluated (22)
• fusion blanket neutronics
• completed (14)
• do be compiled / evaluated (18)
• accelerator shielding
• completed (6)
• do be compiled / evaluated (16)

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SINBAD - Radiation Shielding Experiments
Materials

• B, Ti, H (1)
• C (graphite) (2)
• N (1)
• O (2)
• Na (4)
• H2O (2)
• H2O, C, Fe (1)
• H2O, C, Pb (1)
• H2O, Fe (2)
• H2O, Steel (2)
• H2O, Steel, Al (2)
• Concrete (1)
• Al (1)
• Fe (11)

• Fe, Pb (1)
• Fe, Concrete, (CH2)2n (1)
• Ni (1)
• Si (1)
• Steel (2)
• SS (2)
• Fe SS (1)
• SS (CH2)2n (1)
• SS, (CH2)2n Cu (1)
• Pb (1)
• Si (1)
• V (2)
• Air (1)
• Multiple materials (5)

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IRPhEP - (1/2)Reactor Physics Experiments

• The following types of measurements are included
  
• fundamental mode lattice experiments,
• heterogeneous core configurations
• power reactor start-up data
• specific applications experiments (e.g.
  fission product integral data, irradiation
  experiments)
• Standard / internationally agreed format for
  storage of data / information
• Standard compilation / evaluation / peer review
  procedures approved
• Pilot evaluations carried out to prove method
  adequacy

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IRPhEP - (2/2)Reactor Physics Experiments

• Acceptance criteria for an evaluation
• Description of experimental method
• Description of data handling method
• Specification of corrections if any
• Specific handling of technological uncertainties
• Estimation of biases
• Compliance with formal requirements
• Presentation of sample calculations
• The Levels
• Inventory List
• Storing the primary information
• Preparing the description of the reactor and
  experimental results
• Evaluation of results, their interpretation
  and review
• Storing in a database

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Training / Teaching

• The Frédéric Joliot/Otto Hahn Summer School on
  Modern Reactor Physics and the Modelling of
  Complex Systems will be held at the
  Forschungszentrum Karlsruhe, Germany, from 20-29
  August 2003
• Includes Material Irradiation Damage
  Modelling and Applications
• Training Courses in Radiation Transport Codes
  organised by the OECD/NEA Data Bank in different
  EU Laboratories / Universities
• MCNP, MCNPX, PENELOPE, SCALE codes(Monte Carlo)
• Determinisitic 3D Transport codes (see Web page)
• http//www.nea.fr/html/dbprog/Newsletter/Feb2003.h
  tmtraining

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Conclusions (1/3)

• A large number of experimentalists, physicists,
  evaluators, modelers have devoted large amounts
  of their efforts and competencies to produce the
  data on which the methods we are using today are
  based.
• These data are far from having been exploited
  fully for the different nuclear and radiation
  technologies.
• This wealth of information needs to be preserved
  in a form more easily exploitable by modern
  information technology and for use in connection
  with novel and refined computational models with
  limitations of the past removed.
• These data will form the basis for the studies of
  more advanced nuclear technology, will be
  instrumental in identifying areas where there is
  a lack of knowledge and thus provide support to
  justifying new experiments that would reduce
  design uncertainties and consequently costs

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Conclusions (2/3)

• Improvement of comprehensiveness of the
  databases, experiment re-interpretation and
  re-evaluation using state-of-the-art methods will
  require a large further effort and all
  laboratories wishing to manage and share this
  knowledge are invited to contribute.
• ANS Joint Benchmark Committee (JBC) has adopted
  these formats and procedures
• Recommended by USDoE for NERI Experiments
• Other institutions have expressed the intention
  to document results from ongoing and future
  experiments following these procedures and
  guidelines

Web page http//www.nea.fr/html/scienc
e/integralexps/
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Conclusions (3/3)

• Some valuable shielding and reactor physics
  experiments have been saved in a standard format
  together with the primary documents. These have
  been compiled and reviewed by at least 2 experts.
  
• Further data is being processed and much data is
  waiting to be processed. These experiments have
  been identified of being of high relevance for
  validation of radiation transport and shielding
  methods and codes in support of radiation damage
  / embrittlement studies
• This work is not carried out on a voluntary
  basis, thus funds are needed, in particular for
  assuring peer review. Progress has been slow
  because fund were very scarce.
• PERFECT would be perfect for assuring the
  integration of these new data in support of
  radiation damage / embrittlement studies