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: