CONSYST/ABBN Data Code System
description
Transcript of CONSYST/ABBN Data Code System
CONSYST/ABBN CONSYST/ABBN Data Code SystemData Code System
Gennady ManturovGennady Manturov
(IPPE, Obninsk)(IPPE, Obninsk)
Moscow, June 4-6 2007
ABBN Calculation Scheme
Depletion calculation
s
CONSYST
ABBN-93299 n + 15(127)
P5
GMF format299n+15(127), P5
MMKKENO
TWODANT
MCNP(group mode)
PRECON
Evaluated Nuclear Data
FOND-2.2
NJOY,GRUCON
FFCP(cell code)
MCNP(continuous)
NJOY(ACER)
ACE formatSUBGRAN
(subgroups)
TRIGEX JAR-FR
FACT-BR
GEFEST
SYNTES
Design calculations
CARE-ORIGEN Precise calculations
Con
sta
nts
p
rep
ara
tion
ENDF/B-5, 6JENDL-3JEF-2, 3
RUSFOND
FORMCNP
ABBN-93
The ABBN-93 was prepared from the FOND-2.2 data library (Files Of evaluated Nuclear Data), which contains selected data from JENDL-3, BROND-2, ENDF/B-VI, and JEF-2 libraries. The selection was based on the detailed study of the libraries. It includes checking of the completeness of the data, year of evaluation, comparison of group cross sections, comparison of calculated thermal cross sections and resonance integrals with measured values, comparison of calculated results with experimental results on several fast critical assemblies, etc. During this work, several errors in the data were identified and rectified, some data were modernized. Compiling, modifying and checking of the FOND-2.2 library and retrieving of the group cross sections from the data files was done by Vladimir Koscheev.
RUSFOND
RUSFOND – Russian library of files of evaluated nuclear data Created on the order of the Russian Ministry for Science and Education in 2005 -2006. Contains evaluated nuclear data for all stable nuclides and all radio nuclides with T1/2 > 1 day. The most reliable files were selected from FOND-2.2, BROND-3, JENDL-3.3, ENDF/B-VII, JEFF-3.1 and EAF-2003 (for radio nuclides). The selection was based on cross-checking of the evaluated data one with another and comparison with experimental data from EXFOR. Preliminary neutron data validation through the integral experiments was also made during the selection of the data. As the result of this, different modifications were included in the selected files for many nuclides. It includes files for 654 materials and 20 files of different lows for scatterings in the thermal region
ABBN data tables
ABBN-93 presents group constants for 299 neutron energy groups - from the thermal up to 20 MeV, and for 127 photon groups - from 0 and up to 11 MeV. Resonance self-shielding effects are taken into account by using Bondarenko self-shielding f-factors. Nikolaev's subgroup parameters are also included to 299-group constants sets (they can be used in cases when the spatial dependence of group constants is essential) Effects of neutron thermalization are accounted by P0 and P1 73-grouped thermal scattering matrices in the energy region below 4.65 eV as function of the neutron gas temperature. The ABBN-93 group constants are presented as in the form of formatted tables which can be easily viewed so in binary form. Both data sets (and their combination) can be used in the calculations.
ABBN Verification SchemeABBN Verification Scheme
Microexperiment
evaluation
FORAN
CONSYST
HANDBOOK
MMKKENOTWODANT
MCNP
NJOY
GRUCON
FOND
ABBN-93 g
c e
COREstaistical analysis
biases g ±
ANISN format g
TRIGEXBenchmarkls
g K g
± g
K' c-K e
M ICR O
MACRO
±
± g
new
I N D E C S
PRECONS
evaluation
Macroexperiment
old
LUNDLEMEX
It depends
MICROMICRO Media Media
BROND-2
LIPAR-5
FOND-2.2
JENDL-3
ABBN-93NJOY
ГРУКОН
RUSFOND
- Analysis of measurements of cross-sections- Selection of files- Preparation of group constants- Evaluation of group constants uncertainties
ENDF/B-VIENDF/B-VII
LUND
MACROMACRO Media Media
BFS, КОBRА, МАТR
ZPR,ZPPR, FCA
Analysis
MASURСA,SuperPhenix
BN-600, BN-350,BOR-60
FFCP
MMKKENO
- Analysis of experiments - Creation of benchmarks- International activity
LEMEX
TWODANT
TRIGEX
MCNP
LSENS
IRPhE
ICSBEP
R
R
CORER R
II
IIe
c
exp
calc
EMEX
valuatedacro-periments
LEMEX
LSENS
UN
ncertaintiesuclear
SENS itivityCoefficients
Data
of
I
I
LUND
i j
LTASK
INDECSINDECS System System
Experiments for Neutron Data ValidationExperiments for Neutron Data Validation
Experiment type
233U235U 239Pu
238U232Th
Na
Pb
Bi
Zr, Fe
Cr, Ni
Other
240Pu241Pu
TRU
O, H
N, Si
FPAverage cross sections on the
fission spectrum+ + + + + - + -
Removal cross section under 238U fission threshold
+ + + + - + + +
Spherical transmissions + + + + - + + +Transmissions in the “good”
geometry+ + + + - + + +
Critical experiments with metal U and Pu and solutions of U
and Pu
+ + + + + - + -
Critical experiments + + + + + + + + + + +Critical experiments with
kinf ~1- + + + + + + +
Central average cross
sections ratios+ + + + + + + + + + +
Central reactivity coefficients + + + + + + - - + + + + + + - - - - +Experiments for transmutation
in nuclear reactors+ + + + + + + +
Validation of Structural MaterialsValidation of Structural Materials
Absorption per One Neutron of Source, %
Assembly Fe Cr Ni Mn Mo (Zr)
KBR-7 (Ni) 2 1 41 1 - 45
KBR-9 (SS) 17 7 6 5 - 35
KBR-10 (SS + Mo) 14 6 6 3 11 40
KBR-15 (Cr) 4 31 1 1 - 37
KBR-16 (Zr) 1 1 1 1 40 44
Library KBR-7
Ni
KBR-9
St.Steel
KBR-10
St.Steel & Mo
KBR-15
Cr
KBR-16
Zr
ABBN-93 -1.6 2.7 0.5 4.7 -5.1
ENDF/B-V -3.9 -1.5 -4.0 -15.2 -12.7
ENDF/B-VI.2 0.5 5.9 1.4 9.4 -4.9
ENDF/B-VI.3 0.8 5.2 1.0 8.3 -5.3
ENDF/B-VI.7 -0.8 4.7 0.5 7.7 -5.8
JENDL-3.2 (Isotopic) -2.0 2.9 -0.2 11.5 -7.5
JENDL-3.2 (Natural) -1.4 4.4 1.4 11.9 -7.4
JEF-2.2 0.7 5.9 3.9 12.7 -0.7
FOND-2.2 -0.2 1.9 -0.4 8.3 -7.1
KBR Assemblies
Calculation-Experiment Deviations, %
-ICSBEPICSBEP - NEA/OECD- NEA/OECD, , benchmark experiments on benchmark experiments on
criticality safetycriticality safety- IRPhEP - NEA/OECD- IRPhEP - NEA/OECD, , reactor reactor
physics benchmark experimentsphysics benchmark experiments- BFS-IPPE- BFS-IPPE, , FR mock-up FR mock-up
experimentsexperiments- SINBAD- SINBAD - NEA/OECD- NEA/OECD, , shielding shielding
benchmarksbenchmarks
Used Data Bases
The Big Physical Facility – BFS (IPPE)The Big Physical Facility – BFS (IPPE)
БэнчмаркMCNP
RUSFOND
MCNP ABBN-
RF%
(C/E-1),% ABBN-93
(C/E-1)*100,%
ABBN-RF
SCHERZO-556
0.997650.99722 -0.06 0.31 -0.27
GODIVA 0.99939 0.99997 -0.09 -0.07 -0.06
TOPSY 1.00030 0.99967 -0.06 0.50 -0.02
FLATTOP25 1.00181 1.00089 -0.04 0.30 0.09
BIG-10 0.99778 0.99721 0.06 0.52 0.26239PU JEZEBEL 0.99911 0.99922 0.01 -0.26 -0.10240PU JEZEBEL 1.00092 1.00051 -0.04 0.09 0.08
POPSY 0.99946 0.99881 -0.07 0.20 -0.01
FLATTOP-PU 1.00073 0.99948 -0.12 -0.17 -0.01
Some calculation results with RUSFOND: