experimental (network) and evaluated nuclear reaction data ... · nuclear reaction data at nds n....
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![Page 1: Experimental (network) and Evaluated Nuclear Reaction Data ... · Nuclear Reaction Data at NDS N. Otsuka, V. Semkova, S.P. Simakov, V. Zerkin Nuclear Data Services Unit Nuclear Data](https://reader034.vdocuments.net/reader034/viewer/2022052105/6040410496b4845a59791ec0/html5/thumbnails/1.jpg)
International Atomic Energy Agency
Meeting of A+M Data Centres, 8.09.2011, IAEA, Vienna
1
Experimental (network) and Evaluated
Nuclear Reaction Data at NDS
N. Otsuka, V. Semkova, S.P. Simakov, V. Zerkin
Nuclear Data Services Unit
Nuclear Data Section, IAEA, Vienna, Austria
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International Atomic Energy Agency Meeting of A+M Data Centres,
8.09.2011 2
Experimental nuclear reaction data (EXFOR) http://www-nds.iaea.org/exfor/
Task: Compilation, exchange and dissemination of experimental nuclear reaction data
Organization: International Network of Nuclear Reaction Data Centres
coordinated by NDS
includes14 Centres in 8 Countries (China, Hungary, India, Japan, Korea,
Russia, Ukraine, USA) and 2 International Organisations (NEA, IAEA)
History: 1966 - 1st Meeting of 4 core Centres (Brookhaven, Saclay, Obninsk, Vienna)
1969 - EXFOR adoption as an official EXchange FORmat (X4)
1997 – available via Internet
2000 – implemented as relational multiplatform database
2005 – central global database (master file at NDS)
Status: trusted, increasing and living database (updated 4-5 times per year)
currently (5.09.11): ~19100 experimental works, ~ 141 600 data tables
Mirrors (of whole NDS service): India (BARC) – functioning unstable,
Brazil (IPEN) - looks like nonfuctioning
China (CIAE) - under implementation
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International Atomic Energy Agency Meeting of A+M Data Centres,
8.09.2011 3
Experimental nuclear reaction data (EXFOR), cont. http://www-nds.iaea.org/exfor/
Scope:
- projectile: (compulsory) s.f., n, p, d, t, 3He, α, light ions (A ≤ 12); energy ≤ 1 GeV
(voluntary) γ, e, π, μ, heavy ions (A > 13); higher energy >1 GeV
- targets: isotope/element (T), compound (atom/molecular/substance – T & bounds )
- quantity: total/differential cross sections, resonance parameters, fission yields,
n/γ multiplicities, polarization, thick target yields …
- bibliography: doi and NSR links, pdf-files collection
Network Tools: compilation Control System – selection of articles, control of compilation
(http://www-nds.iaea.org/exfor-master/x4compil/ )
NRDC page: manuals, docs, codes, feedbacks ..
(http://www-nds.iaea.org/nrdc/)
Dissemination: web-retrieval system → different output format (X4, C4, XML ..),
interactive plotting (+ ENDF) …
(off-line, on request) → EXFOR/CINDA databases
on DVD (java + MySQL)
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International Atomic Energy Agency Meeting of A+M Data Centres,
8.09.2011 4
Evaluated nuclear reaction data (ENDF) http://www-nds.iaea.org/endf/
Task: collection, development and dissemination of evaluated nuclear reaction data
Major (national) general purpose libraries (5):
ENDF/B-VII - US Eval. Nucl. React. Data Files (n–393 mat, γ-163, tsl-20, e-20,150 MeV…)
CENDL-3.1 – Chinese Evaluated Data Library
JEFF-3.1 – Joint European Fission and Fusion library
JENDL-4.0 – Japanese Eval. Nucl. Data Lib. (n-406, γ-100, e-100, E< 20 MeV)
RUSFOND-2010 – Russian evaluated files (619 nuclei and 20 materials) for reactors
Special (data for particular applications from labs and persons) libraries (~ 20):
EAF-2010 - European Activation File (816 isotopes, n, p and d, energy up to 60 MeV)
FENDL-2.1 - Fusion Evaluated Nuclear Data Library for ITER neutronics
FENDL-3 - upgrade for Fusion Broader Approach: IFMIF, DEMO (under development)
Standards – 14 neutron induced cross sections with high accuracy (0.1 - 5%)
IBANDL - Ion Beam Analysis Nuclear Data Library for surface analysis of solids
IRDF-2002, DXS … – dosimetry, radiation damage and gas production data
Medical portal – nuclear data for nuclear medicine
….
Dissemination: (on-line) ZVView → σ, σ(E,Θ),Y(FF), Cov(E,E), interactive 2D,-3D-plotting
(off-line, on request) → ENDF (major and special) libraries on DVD
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International Atomic Energy Agency Meeting of A+M Data Centres,
8.09.2011 5
other examples follow on-line …
0 20 40 60 80 100 1200.00
0.05
0.10
0.15
0.20 TSL,UppsalaENDF/B-VII
IEAF-2001
TENDL-2010
Fe(n,x)
JENDL-HE (56
Fe)
INPE-FZK(56
Fe)
LA-150
b
Neutron Energy, MeV
LANSCE
FENDL 3.0 will comprise:
• neutron transport cross-sections up to 150 MeV for 180 materials,
• n-, p- and d-activation cross-sections up to 60 MeV for 816 materials and
• covariances of the evaluated cross-sections
FENDL 3.0 validation against experimental (EXFOR) neutron reaction data:
Example: Fusion Evaluated Nuclear Data Library FENDL 3.0
3H production cross-sections in 23Na He production cross-sections in Fe