Data handling EXTEND Budapest, 1 12 September 2008 Hans Henriksson - - PowerPoint PPT Presentation

Data handling

EXTEND Budapest, 1‐12 September 2008 Hans Henriksson

H Henriksson 1 EXTEND Data handling, 1‐12 Sept 08

Who is the lecturer?

• MSc Engineering Physics, Uppsala University, Sweden.
• PhD in applied nuclear physics (fusion neutron

emission with a magnetic proton recoil spectrometer).

• Researcher at JET, UKAEA Culham during deuterium‐

tritium experiments.

• Nuclear physicist at the OECD Nuclear Energy Agency

(NEA) in Paris.

• Finished the Paris Marathon 2007.

Your background?

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H Henriksson EXTEND Data handling, 1‐12 Sept 08 3

Contents

NEA Data Bank International collaboration Experimental data Evaluated data Applications Tools

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Nuclear data applications

• Nuclear energy: Fission and Fusion
• Accelerator design
• Shielding
• Nuclear waste
• Safeguards
• Medicine
• Environmental monitoring
• Materials analysis
• Dosimetry & radiation safety
• Nuclear astrophysics

H Henriksson EXTEND Data handling, 1‐12 Sept 08 5

NEA Data Bank, Nuclear Data Services

International reference centre for basic nuclear tools, i.e. computer codes and nuclear data for analysis and predictions. Provide a direct service to its users by developing, improving and validating these tools and making them available as requested.

Nuclear data services

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Nuclear data from request to application

Request 2

Presentation Experiment Data Analysis Presentation Experiment Data Analysis

Request n

Check / Validation Processing Codes EXFOR Models, Codes

HPRL

Request Experiment Data Analysis Presentation

Applications

Processed data MCJEFF31 JANIS

Evaluated Data Library

JEFF

ENDF/B JENDL

Theory

7

Evaluation

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International collaboration

Services:

• Coordinates the collect and prepare experimental data and bibliographic

information in EXFOR and CINDA.

• Database web retrievals
• Distribution of nuclear data and computer programs
• Preparation and publication of reports and handbooks

International network of four nuclear reaction data centres (NRDC) was established in 1969:

• OECD / NEA Data Bank, France
• IAEA Nuclear Data Section (NDS), Austria
• National Nuclear Data Center (NNDC), BNL, USA
• IPPE Nuclear Data Center (CJD), Russian Federation

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Specialised centres in the NRDC network

ATOMKI Charged-Particle Nuclear Reaction Data Group, Hungary Centre for Experimental Photonuclear Data, Russian Federation (CDFE) Centre of Nuclear Physics Data (CNPD), Russian Federation Chinese Nuclear Data Center (CNDC), China JAEA Nuclear Data Center, Japan Japanese Charged-Particle Nuclear Reaction Data Group (JCPRG), Japan KAERI Nuclear Data Evaluation Laboratory, Korea Russian Nuclear Structure and Reaction Data Center (CAJAD), Russia Ukraine Nuclear Data Center (UKRNDC), Ukraine

H Henriksson EXTEND Data handling, 1‐12 Sept 08

Nuclear data from request to application

Request 2

Presentation Experiment Data Analysis Presentation Experiment Data Analysis

Request n

Check / Validation Processing Codes Evaluation EXFOR Models, Codes

HPRL

Request Experiment Data Analysis Presentation

Applications

Processed data MCJEFF31 JANIS Evaluated Data EVA

JEFF

ENDF/B JENDL

Theory

10

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NEA Working Party of international nuclear data Evaluation Co‐operation (WPEC) Activities

(http://www.nea.fr/html/science/wpec/) Established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation. Provides a framework for co‐operative activities between the participating projects: BROND, CENDL, ENDF/B, JEFF, JENDL Assesses needs for data improvements and initiates joint evaluation and/or measurement efforts in subgroups to solve problems. Annual meetings are held where the progress in evaluated data and related measurement activities is reviewed. Identification of common problems and setting up of subgroups to solve these problems.

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WPEC Organisation

Europe (JEFF project) 4 members Japan (JENDL project) 4 members USA (ENDF project) 4 members non-OECD (IAEA, Russia, China) 4 members (through IAEA) Subgroup 1 Subgroup 2 Subgroup 3 Subgroup n

Established in 1989, reorganised in 1999 16 members

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WPEC output

• Each subgroup publishes a report
• 23 reports published so far
• Reports available from

www.nea.fr/html/science/wpec/

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Recent WPEC subgroup activities

Subgroup C: High Priority Nuclear Data Request List (HPRL) Subgroup 25: Assessment of fission product decay data for decay heat calculations (Report in 2006) Subgroup 26: Nuclear data needs for advanced reactor systems (Report Aug 2008) Subgroup 27: Prompt photon production from fission products (ongoing) Subgroup 24+28: Production and processing of covariances (ongoing) Subgroup 29:

235U capture cross section in the keV to MeV energy region (ongoing)

Subgroup 30: Improvement of EXFOR accessibility and quality (ongoing) Subgroup 31: Meeting Nuclear Data Needs for Advanced Reactor Systems (new) Subgroup 32: Unresolved resonance treatment for cross sections and covariances (new)

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www.nea.fr/html/dbdata/hprl

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Experimental nuclear reaction data EXFOR

• EXFOR contains information on about 17,300 experiments, divided in 130,000 data sets.
• Neutron as well as charged particle data

Compulsory compilation: A (of projectile) ≤ 12, Ein≤ 1 GeV. Data is collected through:

• Direct contact with the data producer
• Published data or reports publicly available, or sent to the NRDC
• Data only available as graphs (old articles) extracted manually.
• Experimental data, theoretical models and evaluations are collected from all available

literature on nuclear data in the world. Compilation tools include for example:

• Scanning tools to digitize graphical data, e.g GSYS‐2.
• Program to facilitate the compilation, e.g. EXFOR Editor
• Format checking tools, e.g. CHEX and JANIS
• Plotting tools, e.g. ZVView and JANIS
• Conversion tools (output formats), e.g. ENDVER, X4toC4 and JANIS

The EXFOR format Designed for flexibility, to exchange data between centres. End‐user formats for processing and plotting data have recently been improved.

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Measured isotopes in EXFOR

• Stables
• EXFOR data (nat.)
• EXFOR data (isotopic)

Z N

17

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EXFOR basics

EXFOR is the exchange format designed to allow transmission of nuclear reaction data in the NRDC. Data, bibliographic and experimental information is stored.

• An exchange file contains a number of entries (works)

further divided into subentries (data sets). The subentries are further divided into: – bibliographic, descriptive information, – common data that applies to all data in the subentry, – a data table.

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22987

ENTRY

(work)

Subentry

(subwork)

Reaction 1 Reaction n Reaction 2

Sections

DATA

BIB

Data tables Information

COMMON

EXFOR structure

19

001

007

BIB

COMMON

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EXFOR example

ENTRY 22987 20080609 22987 0 1 SUBENT 22987001 20080609 22987 1 2 BIB 9 13 22987 1 3 TITLE Elastic scattering of 96 MeV neutrons from iron, 22987 1 4 yttrium and lead. 22987 1 5 AUTHOR (A.Oehrn, J.Blomgren, P.Andersson, A.Atac,C.Gustavsson,22987 1 6 J.Klug, P.Mermod, S.Pomp, P.Wolniewicz, M.Oesterlund, 22987 1 7 INSTITUTE (2SWDUPP) A.Oehrn, J.Blomgren, P.Andersson, A.Atac, 22987 1 8 REFERENCE (J,PR/C,77,024605,2008) Main reference. 22987 1 9 (T,Oehrn,2008) Exp. details, data analysis. 22987 1 10 FACILITY (CYCLO,2SWDUPP) SCANDAL-Scattered Neutron Det. Assembly22987 1 11 DETECTOR (SCIN) Each of two arms (for 10-50 deg and 30-70 deg) 22987 1 12 ANALYSIS (SHAPE) Background data were subtracted from signal 22987 1 13 ERR-ANALYS (ERR-T) Total error includes statistical, background 22987 1 14 (ERR-S) Relative statistical errors(before corrections)22987 1 15 HISTORY (20080609C) M.M. 22987 1 16 ENDBIB 13 0 22987 1 17 COMMON 5 3 22987 1 18 EN EN-ERR EN-RSL-FW ERR-3 ANG-RSL 22987 1 19 MEV MEV MEV PER-CENT ADEG 22987 1 20

• 96. 0.5 1.2 0.6 1. 22987 1 21

ENDCOMMON 3 0 22987 1 22 ENDSUBENT 22 0 22987 199999 SUBENT 22987006 20080609 22987 6 1 BIB 3 3 22987 6 2 REACTION (39-Y-89(N,EL)39-Y-89,,DA) 22987 6 3 ERR-ANALYS (DATA-ERR) Contains contributions from normalization 22987 6 4 MISC-COL (MISC1) Ratio of data to Wick's limit. 22987 6 5 ENDBIB 3 0 22987 6 6 NOCOMMON 0 0 22987 6 7 DATA 5 1 22987 6 8 ANG-CM DATA-CM DATA-ERR MISC1 22987 6 9 ADEG B/SR B/SR NO-DIM 22987 6 10

• 0. 22.7 2.2 1.09 22987 6 11

ENDDATA 3 0 22987 6 12 ENDSUBENT 11 0 22987 699999 ENDENTRY 7 2298799999999

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Experimental reaction data

A nuclear reaction: A+BC+D

• r

A(B,C)D

(or in EXFOR: SF1(SF2,SF3)SF4,SF5‐SF8 where SF1‐SF4 are ZZ‐SYM‐AA, e.g. 92‐U‐238. Example: 6‐C‐12(P,D)6‐C‐11,PAR,DA = Partial diff. cross sec. dσ/dΩ, of the reaction 12C+p d+11C)

Binding energy: Eb=(Z mp+ N mn‐ mnucl)c0

2= (Z mH+ N mn‐ matom)c0 2

Q‐value: (assume A at rest and all nuclei in ground states): Q = Q0‐E’ = Q0 = ED+EC‐EB = ED

b+EC b‐EB b‐Ea b

Threshold energy: EB

min=‐Q(mA+mB+mC+mD)/2mA≈‐Q(1‐mB/mA)

A D B C θ φ Back

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EXFOR data 22987.002

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EXFOR output formats

NEA: Janis EXFOR output

IAEA: X4+ format output

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EXFOR computational format

EXFOR can be converted to a computational format for facilitating the automated use of experimental data in computer codes and software packages, such as TALYS and EASY.

Back

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History of evaluated nuclear data

• Dunnington (1939), DuMond and Cohen (1953):

Set of recommended values of basic physical constants with uncertainties

• D.J. Hughes (1951). Compilation of neutron data (BNL).
• IAEA was established 1957, with the Nuclear Data Section in 1964.
• Neutron data compilation centre (CCDN), Saclay in 1964 NEA Data Bank
• CJD, Obninsk, Russia, established in 1963.
• ENDF/B‐I (1964), Henry Honeck, 80 nuclei, NNCSC was established in 1967.
• JEF‐1β in 1982 with 70 materials. JEF‐1 was released in 1985 (300 materials)
• JENDL‐1 released in 1977
• Formats:
• EXFOR (experimental data, and evaluated: VIEN‐V),
• KEDAK (Karlsruhe),
• UKNDL (Winfrith)
• EAF (Culham),
• ENDF‐5 et ENDF‐6 (BNL)

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The main evaluated nuclear data libraries

• JENDL‐3.3 was released in 2002 mainly for Japanese FBR, thermal

reactors, fusion neutronics and shielding calculations, 337 isotopes are included.

• JEFF‐3.1 released in May 2005

381 isotopes included in the general purpose (neutron) library. Also: proton files, activation data, radioactive decay data, fission yields, thermal scattering data…

• ENDF/B‐VII.0 released in Dec. 2006: 393 isotopes (n), 14
• sublibraries. Main ref: Nucl data sheets, 107,12(2006)
• BROND‐3, Russia (ver. 2.2 from 1992), CENDL‐3.1 (Chine)
• RIPL‐2 (reference input parameters)
• FENDL‐2.1 (IAEA, fusion),
• IRDF‐2002 (dosimetry),
• EAF‐2007, PADF‐2007 (activation)

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JEFF-3.1

Library

NLIB, NVER, NREL n-induced

Sub-Library

NSUB

Am-241

Material

Z, A, state MF=3

MT=18

File Section

Evaluated data in the ENDF‐6 format

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ENDF‐6 format

• ZA and the MAT Numbers

– ZA = (1000.0*Z) + A. For example, ZA for 238U is 92238.0, and ZA for 9Be = 4009.0. – The MAT number is 100*Z+I where I is unique for the isotope and state, 9237= 238U – (Note, ZA for the element tungsten is 74000.0. The MAT number is 100*Z.)

• Definitions of data types (MF Numbers or files)

– 1 General information – 2 Resonance parameter data – 3 Reaction cross sections – 4 Angular distributions for emitted particles – 5 Energy distributions for emitted particles – 6 Energy‐angle distributions for emitted particles

• Definitions of reaction types (MT numbers)

– 1 (n,total) Neutron total cross section – 2 (z,zO) elastic – 3 (z, non‐elastic) Nonelastic neutron cross section. Sum of MT=4, 5, 16‐18, 22‐26, 28‐37, 41‐42, 102‐116 – 4 (z,n) Cross section for the production of one neutron in the exit channel. Sum of the MT=50‐91. – 5 (z,anything) The cross section for the sum of all reactions not given explicitly in another MT number. – 16 (z,2n) Cross section for producing two neutrons and a residual. – 18 (z,F) Total fission cross section for all incident particles. For neutrons incident, MT=18 is the sum of MT19. 20. 21. and 38. H Henriksson EXTEND Data handling, 1‐12 Sept 08 28

JEFF-3.1 General Purpose Neutron File, May 2005. 2310 0 0 0 8.220800+4 2.061900+2 1 0 2 18237 1451 1 0.000000+0 0.000000+0 0 0 0 68237 1451 2 1.000000+0 2.000000+8 1 0 10 318237 1451 3 0.000000+0 0.000000+0 0 0 665 1478237 1451 4 82-Pb-208 NRG EVAL-DEC04 A.J. Koning 8237 1451 5 NRG-2004 DIST-MAY05 REV1-MAY05 20050504 8237 1451 6

• ---JEFF-31

Material 8237 REVISION 1 8237 1451 7

• ----Incident neutron data 8237 1451 8
• -----ENDF-6 Format 8237 1451 9

***************************** JEFF-3.1 *************************8237 1451 10 ** Original data taken from: New evaluation **8237 1451 12 8237 1451 13 NRG-2004: n + Pb-208 8237 1451 14 8237 1451 15 Author: A.J. Koning, NRG Petten 8237 1451 16 … ************************* C O N T E N T S ************************8237 1451 668 8237 1451 669 1 451 816 18237 1451 670 2 151 88 18237 1451 671 3 1 364 18237 1451 672 3 2 364 18237 1451 673 … 10 104 20 18237 1451 816 8237 1 099999 … 8.220800+4 2.061900+2 0 0 0 08237 3 1 1 0.000000+0 0.000000+0 0 0 1 10838237 3 1 2 1083 2 8237 3 1 3 1.000000-5 4.019707-4 2.530000-2 7.991601-6 1.000000+6 1.500064-48237 3 1 4 … 8237 3 099999 8237 0 0 0

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ENDF format example

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JEFF history

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Isotope chart of JEFF library contents

Z N

• JEFF‐3.1 Neutrons (red)
• JEFF‐3.1/A (blue)
• JEFF‐3.1 RDD (contour)
• EXFOR (green + pink)

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Summary of the JEFF‐3.1 project

General purpose file: JEFF‐3.1 (381 materials) incident proton (26) and thermal scattering data (9) Activation file: JEFF‐3/A

(774 different targets from protons to 257Fm, up to 20 MeV)

Radioactive Decay Data file: JEFF‐3.1.1/RDD

(3852 nuclei, of which 226 stable.)

Fission Yields file:

– JEFF‐3.1/SFY, 19 isotopes from 232Th to 245Cm – JEFF‐3.1/NFY, 3 isotopes: 242Cm, 244Cm and 252Cf

• Web site: www.nea.fr/html/dbdata/JEFF
• JEFF report 21: main reference available from NEA Data Bank

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Energy coverage in JEFF‐3.1

• up to 20 MeV: 338 isotopes
• up to 30 MeV: 9 isotopes
• up to 150 MeV: 12 isotopes
• up to 200 MeV: 22 isotopes

32 Isotopes with covariance data (MF=33)

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Plans for JEFF‐3.2

Main evaluations to be reviewed:

56Fe, Hf, Pb main isotopes, 209Bi, 232Th, 235U, 238U, 237Np, 239Pu, 241Am, 243Am.

Evaluations of delayed neutron data for photo‐fission. Covariance data for important nuclides (collaboration in WPEC). Gamma production data. Photonuclear Data Library. Revision of the Decay Data Library. New evaluations within EFF (52Cr, 55Mn, W, Ta). New Activation Data Library based on EAF‐2007.

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Processing evaluated data

NJOY‐99.259 (latest version) is a system of processing modules intended to convert evaluated nuclear data into forms useful for practical applications. NJOY modules:

• RECONR...reconstruct pointwise cross sections from endf/b resonance parameters and interpolation

schemes.

• BROADR...doppler broaden and thin pointwise cross sections.
• GROUPR...generate self‐shielded multigroup cross sections and group‐to‐group scattering and photon

production matrices.

• ERRORR...construct multigroup covariance matrices.
• COVR...process covariance data from errorr.
• ACER...prepare library for the Los Alamos continuous energy monte‐carlo code MCNP.
• POWR...convert multigroup data into libraries for the thermal powr reactor codes epri‐cell and epri‐cpm.
• WIMSR...convert multigroup data into libraries for the reactor assembly codes wims‐d or wims‐e.
• PLOTR...plot endf, pendf, gendf, or exp. cross sections, distributions, or matrices.
• VIEWR...view plots from plotr, dtfr, covr, etc. in postscript
• MIXR...mix file 3 cross sections (for example, to make elemental cross sections) for plotting, etc.
• PURR...generate unresolved‐resonance probability tables for the MCNP code.

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Application data

Libraries available based on JEFF‐3.1:

MCJEFF31: MCNP libraries at 10 temperatures (300 – 1800 K) WIMS‐D (69 and 172 energy groups) , IAEA website ACE (MCNP) for ADS applications, IAEA website TRIPOLI library

Library based on ENDF/B‐VII.0: MCNP library available from the NEA

Some of the application codes available from NEA:

• ERANOS 2.0: Modular code and data system for fast reactor neutronics analyses
• MCNP/MCNPX: Monte Carlo Particle Transport Code System: MCNP5 1.40, MCNPX 2.5.0, VISED19L and Data Libraries
• MONK: Keff, Collision Rate, Flux Distribution in General Geometry from UKNDL by Monte‐Carlo Method
• OMEGA: Subcritical and Critical Neutron Transport in General 3‐D Geometry by Monte‐Carlo
• SCALE 5.1/ORIGEN‐ARP5.1: Modular system for criticality, shielding, source term, fuel depletion/decay, reactor physics
• SIXTUS‐3, 3‐D: Nodal Neutron Diffusion Criticality in Hexagonal Geometry
• SLAROM: Neutron Flux Distribution and Spectra in Lattice Cell
• TRIPOLI‐4.3.3 & 4.4: Coupled Neutron, Photon, Electron, Positron 3‐D, Time‐depend. Monte‐Carlo, Transport Calculation
• TRITON, 3‐D Multi‐Region Neutron Diffusion Burnup with Criticality Search

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Workshops and training courses

• NJOY user group meetings annually (next in November)
• NEA organised training courses in

– MCNP‐5 / MCNPX – SCALE / TRITON – FLUKA – TRIPOLI

• NEA Data Bank meetings, see

www.nea.fr/html/science/meetings

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JANIS: Java‐based nuclear information software

Nuclide chart Evaluated data libraries, e.g. JEFF, JENDL,ENDF/B Search in EXFOR and CINDA Display data and calculate parameters Compare results Save results as

.csv (text) .png (figures)

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New version of the NEA data display software

Released June 2007 Improved plotting functionality Better export possibilities Completely new CINDA Search page Inclusion of the EXFOR database in original format. Extended EXFOR Search Free download from www.nea.fr/janis (DVD on request)

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JANIS examples (1): Browser

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Data retrieval (IAEA/NDS)

Data retrieval (BNL/ NNDC)

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NEA collections of integral experiments

SINBAD (radiation shielding & dosimetry) ICSBEP (criticality experiments for fuel cycle facilities) IRPhE (reactor physics experiments) IFPE (Fuel performance experiments)

• International benchmark exercises, workshops and

meetings

• Independent verification and validation of

microscopic nuclear data

• Integral Experiments for code and data validation

Criticality benchmarks

High‐enriched uranium with fast and intermediate spectra

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Complete report on validation and full benchmarking of JEFF-3.1 to be published 2008

Model codes

There are several theoretical model codes that are written to produce evaluated data, of which most make use of experimental data, reference parameters, and structure parameters as inputs. Below is a list of the most important model codes at present.

• TALYS‐1:

Software for the simulation of nuclear reactions which provides a complete description of all reaction channels and observable and generates nuclear data for applications. It covers reaction mechanisms over a wide energy range (0.001‐ 200 MeV) and mass number range (12 < A < 339). The optical model and coupled‐channels calculations are done by the ECIS‐06 code.

• EMPIRE‐2.19: Modular system of codes for the modelling of reactions using various

theoretical models, including parameter libraries and EXFOR. It is a tool for basic research and evaluation of nuclear data, combining several theoretical approaches, choosing among alternative input parameters etc.

• GNASH:

Pre‐equilibrium, statistical model cross sections & emission spectra

• STAPRE‐H:

Optical, evaporation & pre‐equilibrium model reaction cross sections

• ECIS‐06:

Coupled channel, statistical model, Schrödinger and Dirac equations

• REFIT‐2007:

Multilevel resonance parameter least square fit of neutron transmission and capture data

• SAMMY‐7:

Multilevel R‐matrix fits to neutron and charged‐particle cross sections using Bayes' equations.

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NEA Computer program services

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Other relevant nuclear data activities

Examples of IAEA Coordinated Research Projects CRPs

• RIPL‐3 (started in 2004)
• Updated decay data library for Actinides (2005)
• Reference database for prompt gamma‐ray neutron activ. Anal., PGAA (2005)
• Nuclear data for ion beam analysis, IBANDL (2005)
• Heavy charged‐particle interactions data for radiotherapy (2007)
• Minor actinide neutron reaction data, MANREAD (2007)
• Nuclear data libraries for advanced systems: Fusion devices, FENDL‐3 (2008)

Other data development activities

• IRDF‐2002 dosimetry library (extension to higher energies and inclusion of covariances.
• Updates to WIMS‐D library package, including new decay and fission product yield data
• Beta decay and decay heat meetings (project with the IAEA and NEA WPEC Subgroup 25)
• Neutron data for Cd in the RRR, experimental data from IRMM, Geel, including res. param.
• Handbook of Nuclear Data for Safeguards: www‐nds.iaea.org/sgnucdat/vchart/vsafeg.htm

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Nuclear data web pages and on‐line tools

• The NEA Data Bank: www.nea.fr/html/dbdata/

(Links to EXFOR, JEFF and other evaluated libraries, processing codes, …)

• The JANIS home page: www.nea.fr/janis

(Download program, documentation, help pages…)

• The IAEA nuclear data page:http://www‐nds.iaea.org/

(Databases, structure data, format manuals)

• JAEA Nuclear Data Center

http://wwwndc.jaea.go.jp/nucldata/usefulL.html (Several links to evaluated and experimental data)

• The NNDC, BNL, USA

http://www.nndc.bnl.gov/

• The Q‐value calculator:

http://nucleardata.nuclear.lu.se/database/masses/ (Several other useful tools regarding basic nuclear properties)

• The Los Alamos (T2) data page: http://t2.lanl.gov/

(Codes and data are collected and maintained, such as the code NJOY, see ‘Codes’)

• JEFF

http://www.nea.fr/html/dbdata/JEFF/

• ENDF/Bhttp://www.nndc.bnl.gov/csewg/
• JENDLhttp://wwwndc.jaea.go.jp/jendl/jendl.html
• BROND http://www.ippe.obninsk.ru/podr/cjd/
• CENDL http://www.ciae.ac.cn/ciae.htm
• FENDL http://www‐nds.iaea.org/fendl21/

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