Tools for Criticality Safety Validation Developed in ... meeting/SKALA... · Tools for Criticality...

Paris, December 5-6, 2007 1

Tools for Criticality Safety Validation Developed in Institute

for Physics and Power Engineering

(The SKALA System for Criticality Calculations and Evaluation ofUncertainty of the Criticality Calculations)

Yury Golovko

Obninsk, Institute for Physics and Power Engineering, Russia(e-mail: [email protected] )


SKALA - 2007The SKALA code package was developed as a tool for computerized analysis of nuclear safety problems.

The SKALA code package incorporates many basic calculation codes, libraries, subsidiary modules. It manages automatic operation of code sequences, converts data from one format into another, presents results of calculation in a suitable form. It allows the user to describe a problem using one input-file while many codes to be run have different input-files.


SKALA - 2007The capability of calculating both criticality and its uncertainty caused by errors as in nuclear densities so in neutron data is the major distinction of new version of the SKALA package.

Further, the initial value of keff can be essentially improved by taking into account a set of selected benchmark experiments included in SKALA data banks.

By analyzing benchmark’s C/E-values as well as evaluated uncertainty bars and correlations, a bias in the initial value of keff is derived.

As the result, the part of uncertainty caused by neutron data is usually essentially reduced.


Program realizationThe SKALA code package is organized as groups of executable

modules and data files situated in special directories. The control module SKALA.EXE and the configuration file SKALA.CFG are situated in the main directory whose name and location are set by a user, whereas the structure and location of other files arefixed in SKALA.CFG. This file also contains descriptions of calculational profiles. A profile is an algorithm which describes a sequence of running different codes, checks quality of their operation and controls exchange of information. Each profile wascoded in a special language and could not be modified by a user.


“INDECS” profile – example (SKALA.CFG)INDECS Greeting= SKALA - IS THE SYSTEM FOR COMPUTERIZED ANALYSIS, OF NUCLEAR CRITICALITY AND RADIATION SAFETY, ON THE ATOMIC INDUSTRY PLANTS, ABBN Laboratory (c)2001-2006, , Phone: +7 48439 95421, e-mail: [email protected] [email protected], Obninsk. Kaluga region. Russia, , (Sensitivity/uncertaintyes calculations ) Ver= 134 OutputType= Binary Entry= 40 Variables=CONSEXE, MCNP, LEMEX, LUND Commands= copy:[PROGRAMS]run386.exe [PathRunCurrent]run386.exe , IF:(NotExist([CONFIG])) goto:noConfig , merge:[CONFIG] CONFIG.DRV , * merge:CONFIG.DRV [CONFIG] , * move:[CONFIG] CONFIG.DRV , "CONFIG"copy:CONFIG.DRV [DISPLAY] , :noConfig IF:(Exist([CONSYST])) goto: consOk , IF:(Exist([CONS9901])) ren:[CONS9901] [CONSYST] , IF:(Exist([CONS9900])) ren:[CONS9900] [CONSYST] , :consOk IF:(NoControl) GOTO:noContr0 , IF:(Control(0)=ARCHIVE) IF:(NotExist([PATHJOB]ARCHIVE)) md:[PATHJOB]ARCHIVE , IF:(Control(0)=ARCHIVE) copy:[PATHJOB][NAMEJOB] [PATHJOB]ARCHIVE\[NAMEJOB] , IF:(Control(0)=CALCONLY) GOTO:Spectr , :noContr0 LET:CONSEXE= &run386.exe -nosignon [PROGRAMS]CON9901b.EXE , LET:MCNP=5 , IF:([ABBN]=ABBN90) LET:CONSEXE= &run386.exe -nosignon [PROGRAMS]ABBN90\CONSYST.EXE , IF:([ABBN]=ABBN931) LET:CONSEXE= &run386.exe -nosignon [PROGRAMS]CONS9900\CONS9900.EXE , IF:([ABBN]=9301A) LET:CONSEXE= &run386.exe -nosignon [PROGRAMS]CONS9901\CONS9901.EXE , IF:([ABBN]=RSICC) LET:CONSEXE= &run386.exe -nosignon [PROGRAMS]RSICC\CON5M.EXE , --------------------------------------------------------------- . About 500 rows in this frofile only


The principle scheme of SKALA

The new profiles of SKALA enable to make the following types of calculations:Criticality calculations;Estimation of the criticality uncertainty caused by errors in nuclear densities;Estimation of the criticality uncertainty caused by errors in neutron data;Determination of the systematic bias which is derived from statistical analysis of integral experiments.Determination of the criticality uncertainty which remains after taking into account a bias.


Executable modules:CONSYST – the group constant preparation code using the group constant library ABBN93;MMKKENO – the 3-dimensional Monte Carlo neutron transport code; it calculates criticality and its derivatives with respect to macro-constants using;TWODANT – the 1- and 2-dimensional discrete ordinate neutron transport code; it calculates forward and adjoint neutron fluxes;KEFSF – this code computes derivatives of criticality with respect to macro-constants using the first order perturbation theory;SENSIENCE – this code converts derivatives into sensitivities;CORE50 – the uncertainty analysis code; this part of the INDECS code package calculates the uncertainty of criticality caused by errors in neutron data and, by means of statistical analysis of integral experiments, estimates a bias;UNCERT – the uncertainty analysis code; it calculates uncertainty of criticality; caused by errors in nuclear densities;UNCERMAC – the uncertainty analysis code; it calculates the uncertainty ofcriticality caused by errors in neutron data without applying to INDECS;FORLUND – the codes of converting covariances from the MACOVCA format to the LUND one;FORMAC – the codes of making covariances in the MACOVCA format;



LibrariesABBN – the group constant library (group constants, Bondarenko’s, etc.);GMF – this file is formed by CONSYST; it contains all the input- and output-data of the code and serves as a data file for sensitivity codes;LSENS – the library of INDECS which keeps sensitivities for the application and a numerous set of integral experiments;LEMEX – the library of INDECS which keeps integral experiment covariances;LUND – the library of INDECS which keeps neutron data covariances;MACOVCA – this library keeps neutron data covariances; it partly duplicates LUND. (New format bellow)



The principle scheme of SKALA “INDECS” profile

∆σ- n

ABBN

CONSYST

CORE50

SENSIENCE

LSENS LEMEXLUND

INDECS

UNCERT

SKALA OUTPUT

SKALA INPUT DATA

σ

σ~

σσ

∂∂ a

a

kk

LSENS-A

σσ

∂∂ exp

exp

kk

expkδδσ

σδ ak

ρδ ak

stataa kk δ±

222 )()()( ρσ δδδ aastataa kkkk ++±

⎥⎥⎥

⎦

⎤

⎢⎢⎢

⎣

⎡+⎥⎥⎥

⎦

⎤

⎢⎢⎢

⎣

⎡−−

=option

ncalculatioderivative

MMKFKVIKENO

aVKENOMMKKENO

.

MACOVCAAdjust-n

FORLUND

Σ∂∂ a

a

kk1

GMFTWODANT

σδ ak

FORMAC

σδ ak

MACOVCA Cov Mat WinMMKKENO

KEFSF


The sensitivity coefficients calculation for the each material of the core by SENTIENCE module.

For the following cross sections:

- number of fission neutrons per fission- fission - capture- elastic scattering- inelastic scattering- average cos scatetring- fission spectra

The principle scheme of SKALA “INDECS” profile


The principle scheme of SKALA “Criticality” profile

∆σ- n

ABBN

CONSYST

SENSIENCE

SKALA OUTPUT

SKALA INPUT DATA

σ

σ~

σσ

∂∂ a

a

kk

LSENS-A

δσ

ρδ ak

stataa kk δ±


⎥⎥⎥

⎦

⎤

⎢⎢⎢

⎣

⎡+

⎥⎥⎥

⎦

⎤

⎢⎢⎢

⎣

⎡−−

=option

ncalculatioderivative

MMKFKVIKENO

aVKENOMMKKENO

.

MACOVCAAdjust-n

UNCERMAC

Σ∂∂ a

a

kk1

GMF

σδ ak

MACOVCA CovMatWin

adjustδσσ∆

MMKKENO TWODANT

KEFSF


MACOVKA Edited (CovMatWin)


Cov. matrices library (MACOVKA)

the list of reactions the covariance data of which are available in SKALA.

- total cross section

- radiation capture cross section

- fission cross section

- number of neutrons per fission

- elastic and inelastic cross section

- the (n,2n) reaction cross section

- average cos. scattering

gtσgñσgfσ

gfν

'' , ggin

ggel

→→ ΣΣg

nn )2,(σgfµ


the list of isotopes and the covariance data of which are available in SKALA.

fissile:Th-232, U-233, U-234, U-235, U-238, Pu-239, Pu-240, Pu-241

Non fissile:H, B, C, N, O, F, Al, Cr, Fe, Ni

Cov. matrices library (MACOVKA)


Uncertainness calculations in “Criticality” profile

This component of the total uncertainty is calculated as the following:

This component of the tech.(concentration) uncertainty is calculated as the following:

This component of the total uncertainty is calculated as the following (including macro experiments):

Neutrons multiplification factor shift

∑∆=∆x

xxeff Sk *σ imin

imel

imfiss

imcap SSSSx ,,,,>−−−

imin

imel

imfiss

imcap SSSSP ,,,, +++>−−−

2const

k∆ = PTWmicroP

2techk∆ = PTWconcP

2const

k∆ = PTWadjustP


The principle scheme of SKALA coordination“Criticality” and “INDECS” profiles

∆σ- n

ABBN

LSENS

LEMEX

LUND

INDECS

SKALA OUTPUT

SKALA INPUT DATA

σ

σ~

σσ

∂∂ a

a

kk

LSENS-A

σσ

∂∂ exp

exp

kk

expkδδσ

ρδ ak

stataa kk δ±


⎥⎦

⎤⎢⎣

⎡⎥⎦

⎤⎢⎣

⎡+−

−

=

option

ncalculatio

derivative

MMKFK

VIKENO

aVKENO

MMKKENO

.

MACOVCAAdjust-n

Σ∂∂ a

a

kk1

GMF

σδ ak

σδ ak

MACOVCA CovMatrixWin

CONSYST

TWODANT

KEFSF

SENSIENCE

FORLUND

CORE50

UNCERT

MMKKENO

CRITICALITY∆σ- n

MACOVCAAdjust-n

FORMAC

UNCERMAC

ρδ ak σδ ak

adjustδσ

σ∆δσ

σσ

∂∂ a

a

kk

σ∆ adjustδσ

δσ


List of available covariance matrices(30 energy grouped structure)

Ni101N101234U

Fe2, 251C239Pu 101, 4, 2

Cr10110B238U

101, 2Al101, 2H235U

101F241Pu233U

2, 251O452, 18, 101

240Pu

452, 18, 101,4, 2, 251

232Th

Reac.NuclideReac.NuclideReac.Nuclide


Criticality Prediction Uncertainty Caused by Nuclear Data and Composition

-----------------------------Without Critical Experiments-----------------------------NAME NU (N,F) (N,CAP) (N,N') (N,N) CONCU234 0.01* 0.01* 0.01 - * - * 0.00*U235 0.49 1.34 0.60 0.15 0.03* 0.29 U238 0.16 0.26 1.63 1.00 0.01 0.15 O 0.06 0.05* 0.05 0.01*C - * - * 0.08* 0.02*SI - * - * - * 0.00*TI - * - * - * 0.00*CR 0.03 0.01 0.01 0.03*MN 0.03* 0.01* 0.01* 0.00*FE 0.07 0.06 0.01 0.04NI 0.03 - 0.01 0.02*AL 0.03 0.07 0.01 0.08*TOTAL 0.52 1.37 1.74 1.02 0.10 0.34

* - Adopted uncertainty in the case of absence data in the library:NU (N,F) (N,CAP) (N,N') (N,N) CONC

5.00% 10.00% 30.00% 30.00% 20.00% 5.00%K-effective= 0.9925 +/- 0.0252 Components of Total Uncertainty:

0.02% - Statistics2.50% - Nuclear Data

(0.10 % - uncertainty included in *)0.34% - Concentrations

(0.09 % - uncertainty included in *)


Criticality Prediction Uncertainty Caused by Nuclear Data and Composition

------------------------------------------Taking into Account Critical Experiments------------------------------------------NAME NU (N,F) (N,CAP) (N,N') (N,N) CONCU234 0.01* 0.01* 0.01 - * - * 0.00*U235 0.41 0.89 0.44 0.10 0.03* 2.29*U238 0.15 0.23 0.88 0.31 0.01 0.15O 0.06 0.05* 0.04 0.01*C - * - * 0.08* 0.02*SI - * - * - * 0.00*TI - * - * - * 0.00*CR 0.02 0.01 0.01 0.03*MN 0.03* 0.01* 0.01* 0.00*FE 0.07 0.06 0.01 0.04NI 0.03 - 0.01 0.02*AL 0.03 0.07 0.01 0.08*TOTAL 0.44 0.92 0.99 0.35 0.09 0.34

* - Adopted uncertainty in the case of absence data in the library:NU (N,F) (N,CAP) (N,N') (N,N) CONC

5.00% 10.00% 30.00% 30.00% 20.00% 5.00%K-effective= 0.9975 +/- 0.0050 Components of Total Uncertainty:

0.02% - Statistics0.36% - Nuclear data

(0.10 % - uncertainty included in *)0.34% - Concentrations

(0.09 % - uncertainty included in *)


CONCLUSIONSThe SKALA system integrates experience of carrying out of calculations according to critical experiments (algorithms and methods).The SKALA system integrates libraries and the data received as a result of these activities.Application of the system allows to minimize mistakes in the applications of the BIG complex of programs and libraries:

Provides interaction of the mentioned above libraries and programs with transfer of the intermediate data without participation of userAllows to formalize (to describe in simple and clear «User manual») application of so complicated system.Automates some formal operations connected to preparation and transformation of the intermediate data, tasks, and libraries

Used in the system MMKKENO program with the algorithm of calculation by a Monte Carlo method allows to exclude methodical component of an error in most cases .The SKALA estimates of a constant component of uncertainty and also allows to minimize it. The databank by results of the integrated (critical) experiments, included in system is used.Allows to carry out fast serial calculations and avoid using complex (INDECS) having essential restrictions.The complex is designed both for skilled expert and for formal user which wants to calculate constant and technological component of the calculation most simply.The SKALA system allows not only to calculate k-eff for given system but also to estimate uncertainty in this calculation (technological and constant) without which knowledge the analysis of problems of nuclear safety is essentially complicated.

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