Nuclear Data Evaluation Activities in KAERI

KAERI / NDELKAERI / NDEL1st RCM FENDL-3 CRP IAEA Dec 2-6

Nuclear Data Evaluation Activities in KAERI

Hyeong Il Kim*

Nuclear Data Evaluation Lab.,Korea Atomic Energy Research Institute

*E-mail: [email protected]

- - 22 - -KAERI / NDELKAERI / NDEL

1st RCM FENDL-3 CRP IAEA Dec 2-6

Table of Contents

Introduction

Evaluation Procedure Extension of EMPIRE-II ECISPLOT

Benchmark tests for FENDL-2.1

Recent Evaluation Results Neutron induced reactions (W) Charged particle induced reactions (Al)

Summary and Further Works



Introduction

Nuclear Data Evaluation Lab. (NDEL) Staffs (8+1)

Evaluation (4), Processing & Benchmark (4), and Secretary (1)

Recent achievements Evaluation (contributed to ENDF/B-VII.0)

32 FPs collaborated with BNL 124 Photonuclear Evaluations ( IAEA-CRP)

Processing (contributed to NEA/DB) MATXS-format 150-group neutron libraries for fast reactors:

KAFAX-E70 (ENDF/B-VII.0), KAFAX-F31 (JEFF-3.1), and KAFAX-J33 (JENDL-3.3),

Benchmark Integral tests for ENDF/B-VII.0, JEFF-3.1, JENDL-3.3 and so on. Al, Fe, Ni, Si, and W (FENDL-2.1)



Cont’d

Recent Activities related with FENDL Library Motivated by our benchmark results for FENDL-2.1

Oktavian (Al, Si, Ni, Fe, W) FNS, Criticality benchmark (W)

New 182,183,184,186W evaluations up to 20 MeV (EMPIRE-II) Individual channels were in good agreements with

measurements. Integral measurements are reproduced well. They are being extended to 150 MeV including the

covariance files. d- and p- induced reactions for 27Al (Talys)

In addition, doing the evaluations for n-, d-, and p- induced reactions on Si, Ni and Fe



Evaluation Procedure



Evaluation, Processing and Benchmark

Nuclear Reaction codes EMPIRE-II (Neutron), TALYS (Charged Particles) Initial Input data taken from RIPL-II ( next RIPL-III) OMP optimized by ECISPLOT Nuclear models by comparison with measurements

Evaluation Check Not only individual channels but also the Integral tests Almost no manual works to produce the ENDF-6 formatted

files except the complaints by checking codes from time to time

Extension of EMPIRE to resonance module in collaboration with BNL

Processing (Njoy-99.161) Benchmark (MCNPX-2.5.0)



Determination of covariances: Uncertainties compiled in the Atlas used as a basis Missing uncertainties are estimated Correlations between resonance parameters can be introduced Ensuring consistency between uncertainties assigned to parameters for the first few

resonances and experimental uncertainties for the thermal cross sections

The resonance module: Reads data from the electronic version of the Atlas Makes statistically justified guesses for unknown parameters Uses average resonance properties to construct unresolved resonance region Allows manual adjustment of parameters, their uncertainties, energy ranges,

average quantities Creates ENDF-6 files MF = 2 and MF = 32

EMPIRE-II Resonance module with Covariance



Graphical User Interface (GUI)

Extension of EMPIRE-II (cont’d )



Extension of EMPIRE-II (cont’d )

Graphical analysis of resonance energies - helps to determine the upper boundary of the resolved resonance region.

Plot of the Porter-Thomas distribution - helps to determine the average resonance parameters such as a level spacing and neutron strength functions for s- and p-waves.

Comparison of cross sections with experimental data and ENDF/B-VII.0 for Total cross sections



ECISPLOT

Fitting or searching OMP parameters using the results of ECIS cal.

Automatic Fit: Simulated Annealing (SA) Manual Fit Reads C4 formatted files for experimental data Reads and writes the RIPL-2 format for OMP

Directly used as inputs of EMPIRE and TALYS

Being still developed Fast for spherical OMP but slow for CC OMP

Going to Parallel computing

Available new formula



Benchmark tests for FENDL-2.1

< Distribution of materials by original source of evaluation in FENDL-2.1 >< Distribution of materials by original source of evaluation in FENDL-2.1 >

Material Library

22H, H, 33H, H, 44He, He, 66Li, Li, 77Li, Li, 99Be, Be, 1010B, B, 1111B, B, 1616O, O, 1919F, F, 28-3028-30SiSi, , 3131P, S, P, S, 35,3735,37Cl, K, Cl, K, 50,52-5450,52-54Cr, Cr, 54,57,5854,57,58FeFe, , 5959Co, Co, 61,62,6461,62,64NiNi, , 63,6563,65Cu, Cu, 9797Au, Au, 206-208206-208Pb, Pb, 209209Bi, Bi, 182-182-

184,186184,186WW

ENDF/B-VI.8ENDF/B-VI.8

11H, H, 33He, He, 2323Na, Na, 46-5046-50Ti, Ti, 5555Mn, Mn, 92,94-98,10092,94-98,100Mo, Mo, 181181Ta, VTa, V JENDL-3.3JENDL-3.3

Mg, Ca, GaMg, Ca, Ga JENDL-3.2JENDL-3.2

1212C, C, 1414N, Zr, N, Zr, 9393NbNb JENDL-FFJENDL-FF

2727AlAl, , 5656FeFe, , 5858NiNi, , 6060NiNi JEFF-3.0 (EFF)JEFF-3.0 (EFF)

1515N, SnN, Sn BROND-2.1BROND-2.1

Oktavian

Pulsed sphere experiments for neutron and gamma-ray leakage spectra at the D-T neutron source facility of Osaka University

Benchmarks for Ni, Fe, Al, Si, and W spheres taken from SINBAD



Gamma leakage spectrum (Al)

100 10110-4

10-3

10-2

10-1

100

L

ea

kag

e S

pe

ctru

m (

/Me

V/S

ou

rce

)

Energy (MeV)

OKTAVIAN-Al (Gamma) ENDF/B-VII.0 JEFF-3.1 JENDL-3.3 FENDL-2.1 Gamma Measurement



Gamma leakage spectrum (Si)

0 1 2 3 4 5 6 7 8 9 1010-3

10-2

10-1

100

L

ea

kag

e S

pe

ctru

m (

/Me

V/S

ou

rce

)

Energy (MeV)

OKTAVIAN-Si (Gamma) ENDF/B-VII.0 JEFF-3.1 JENDL-3.3 FENDL-2.1 Gamma Measurement



Neutron leakage spectrum (Ni)

0 2 4 6 8 10 12 14 1610-3

10-2

10-1

100

L

ea

kag

e S

pe

ctru

m (

/Me

V/S

ou

rce

)

Energy (MeV)

OKTAVIAN-Ni ENDF/B-VII.0 JEFF-3.1 JENDL-3.3 FENDL-2.1 High Energy Measurement



Neutron leakage spectrum (W)

10-1 100 10110-2

10-1

100

101

L

ea

kag

e S

pe

ctru

m (

/leth

arg

y/S

ou

rce

)

Energy (MeV)

OKTAVIAN-W (Neutron) ENDF/B-VII.0 JEFF-3.1 JENDL-3.3 FENDL-2.1 Neutron Measurement



Tungsten Evaluation



Capture cross sections



(n,2n) cross sections



Neutron Production



Oktavian



FNS



Criticality Benchmark



Charged particle induced reactions

d-, p- and a- induced reactions TALYS-0.72 (=>TALYS-1.0) Incident energy: up to 150 MeV Modified OMP



Proton Induced Reactions



Production cross sections induced by proton



Residual Cross Sections induced by Proton



Deuteron Induced Reactions



Alpha induced reactions



Summary and Further works

Summary Evaluation based on EMPIRE-II, TALYS, ECISPLOT codes Performed Benchmark tests for 5 materials in the FENDL-2.1

library. Completed evaluations on four tungsten isotopes up to 20 MeV

and extending 150 MeV including covariance files. Calculated p-, d-, and a- induced reactions for 27Al.

Further works Short term: Evaluations for n-, d-, p- induced reactions on Al, Si,

Ni, and Fe Long Term: Pre-emptive improvement of nuclear data for future

nuclear R&D applications

Nuclear Data Evaluation Activities in KAERI

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