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2.405200+4 5.149380+1 1 0 2 3
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 296 1
24-Cr- 52 IRK,CEA EVAL-DEC95 S.TAGESEN, H.VONACH, O.BOULAND
EFF-DOC DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 2431 REVISION 3
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** Program FIXUP (Ver. 2002-1) used to create MF3/MT3,4 **
******************************************************************
******************************************************************
* *
* EEEEEEEE FFFFFFFF FFFFFFFF 3333333 000 *
* E F F 3 0 0 *
* E F F 3 0 0 *
* EEEEEE FFFFFF FFFFFF 3333333 * 0 0 *
* E F F 3 0 0 *
* E F F 3 0 0 *
* EEEEEEEE F F 3333333 000 *
* *
******************************************************************
EUROPEAN FUSION FILE VERSION 3.0
--------------------------------
The European Fusion File is a project of various European
laboratories and is sponsored by the European Fusion Programme of
the European Union.
The data file EFF-3.0 is maintained at the:
OECD Nuclear Energy Agency
Nuclear Data Services
Le Seine St-Germain
12 boulevard des Iles
92130 Issy-les-Moulineaux
FRANCE
Email: db@nea.fr
******************************************************************
AUTHORS OF THIS DATA FILE:
- S. Tagesen and H. Vonach, IRK Vienna.
- O. Bouland, CEA Cadarache.
******************************************************************
HISTORY
89-12 -NEW EVALUATION AT E > 1 MEV WAS MADE BY M. UHL (IRK-
VIENNA) SEE REF. /1/
90-05 -RESONANCE PARAMETERS FROM JEF-2 /2/ EVALUATION INSER-
TED
90-05 -PHOTON-PRODUCTION DATA OF IRK ADDED
90-05 -FINAL EVALUATION ISSUED /3/
90-08 -MF33 DATA ADDED, INCLUDING REVISIONS TO
...FILE 1 FOR COMMENTS AND TABLE OF CONTENTS
BY S. TAGESEN AND H. VONACH (IRK-VIENNA)
90-11 -MF34 DATA ADDED, INCLUDING REVISIONS TO FILE 1
BY S. TAGESEN AND H. VONACH (IRK-VIENNA)
95-12 -complete reevaluation of MF3+MF33 above .637MeV
BY S. TAGESEN AND H. VONACH (IRK-VIENNA) /5/
01-09 -new data added for MT 1, 2, 16 and 51, eval.threshold
increased to 1.2 MeV to be consistent with new MF 2
evaluation by Olivier Bouland (2001)
01-11 -The fine structure was superimposed on the total cross
section. Contribution from minor isotopes was subtracted
(adopting ENDF/B-VI.7 cross sections) (A.Trkov)
02-01 -(n,t) and (n,He3) cross sections from IEAF-2001 file were
inserted together with corresponding covariance files
evaluated by S.Tagesen and H.Vonach (IRK-Vienna).
02-03 -MF2 and MF4MT2 replaced by new evaluation of O. Bouland
MF 6, 12, 14 and 15 replaced by ENDF-B 6.2
05-04 -MF6/MT16,22,28,91 replaced by A. Koning using new
results from TALYS. This repairs a significant
underestimation of the compound neutron peak.
************************************************************
------ DESCRIPTION OF FILES
(MF - MT)
1 - 451 HISTORY OF EVALUATION, GENERAL INFORMATION AND
DEFINITIONS
2 - 151 -------------- RESONANCE PARAMETERS ------------
Olivier Bouland (CEA/DRN/DER/SPRC/LEPh) 01/27/99
(see JEF/DOC 786 and NSE 137, 70-88 (2001))
A Bayesian fit was performed with the code SAMMY (LA98)
from the following experimental data set:
the thermal capture cross section of Pomerance (PO52),
the thermal scattering cross section of Koester (KO78),
the capture cross section measurement of Kapchigashev (KA64),
the ORNL high resolution transmission measurement (HA95) and
the GEEL high resolution transmission measurement (RO89).
Reich-Moore resonance parameters obtained from this fit
give theoretical cross sections in agreement with the
measured data. To take into account levels outside the
energy range of this analysis, two sets of fictitious levels
were constructed: the first set contains 18 fictitious bound
levels which also allow to reach the values measured for the
thermal partial cross sections and the second set includes
19 positive fictitious levels above 1.4 MeV.
In a preliminary fit from the ORNL high resolution elastic
scattering cross section measurement (HA96), spin and parity
of resonances were assigned with some degree of confidence in
the range 0-1.0 MeV. Resonance parameters given in file 2 151
are available for computing total, elastic and capture cross
sections in the energy range 0-1.2 MeV. No additional smooth
correction cross sections are needed. Resonance parameters
given in the energy range 1.2 - 1.4 MeV are those of true
resonances seen in transmission but these parameters are not
expected to represent correctly the scattering cross section.
The calculation with the Blatt and Biedenharn formalism of
the angular distribution of the elastic cross section is
encouraged from the resonance parameters in the energy range
0-1.0 MeV. Since NJOY do not allow the reconstruction of the
differential elastic scattering cross section from the reso-
nance parameters with the Blatt and Biedenharn formalism, the
angular distributions, represented as Legendre polynomial coef
-ficients in the center of mass system, were tabulated in the
file 4 2. A new covariance file 33 is planned for the cova-
riances of neutron cross sections.
Capture widths:
---------------
Since no capture cross section data above 50 keV were
available for this re-evaluation, values published by Rohr et
al. (RO89) for g*capture width and/or capture areas were used
in the energy range below 500 keV. For small resonances and
for resonances above 500 keV, the value of the capture width
was fixed to the corresponding average capture width.
Average capture widths chosen (in eV):
s-wave resonances 1.32
p-wave resonances 0.45
d-wave resonances 0.65
Thermal constants This work (b) experimental data (b)
capture 0.76 0.76+-0.06 [PO52 also MU81]
scattering 2.96 2.96+-0.02 [KO78 also MU81]
-------------- REFERENCES FOR RESOLVED RANGE -------------
LA98 N.M.LARSON, ORNL/TM-9179/R4 (DEC 1998)
HA96 J.A.HARVEY, 52Cr SCATTERING MEASUREMENT (200 FLIGHT
PATH), PRIVATE COMMUNICATION (Nov. 1996)
HA95 J.A.HARVEY, 52Cr TRANSMISSION MEASUREMENT (200 FLIGHT
PATH), PRIVATE COMMUNICATION AT ORNL(1995)
RO89 G.ROHR et al., PHYS.REV.C39,2 (1989) 426
MU81 S.F.MUGHABGHAB ET AL. NEUTR.CROSS SECT. VOL.1,PART.A,
(1981)
KO78 L.KOESTER et al., Atoms and Nuclei 272 (1978)
KA64 S.P.KAPTSHIGASHEV et al., AE 16, 256 (1964)
PO52 H.POMERANCE, PHYS.REV. 88,2,412 (1952)
3 - 1 THE TOTAL CROSS-SECTION WAS OBTAINED FROM 1.2 MeV
TO 20 MEV BY GLUCS evaluation for Cr-nat(see ref. /5/ )
The fine structure observed in the most recent high-
resolution experiment [Larson 96] from Aak Ridge was
superimposed on the total cross sections as follows:
* Oak Ridge high resolution data for Cr-nat were
thinned to piecewise-linear form within reasonably
acceptable tolerance, thus reducing the number of
points.
* The linearised data were renormalised to the GLUCS
output.
* Contribution of the minor isotopes was subtracted
to yield the total cross section of Cr-52. The
ENDF/B-VI.5 cross section values were adopted for
the minor isotopes. Note that these isotopes have
resonance structure in the cross sections up to
about 10 MeV.
* The linearised and renormalised Oak Ridge data,
corrected for the minor isotopes were inserted into
the file from 1.2 to 10 MeV.
3 - 2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY
SUBTRACTING THE NONELASTIC FROM THE TOTAL
3 - 16 (N,2N) CROSS-SECTION BY GLUCS evaluation.
3 - 22 (N,NA) + (N,AN) CROSS-SECTIONS BY GLUCS evaluation.
3 - 28 (N,NP) + (N,PN) CROSS-SECTIONS BY GLUCS evaluation.
3 - 51-60 INELASTING SCATTERING EXCITING DISCRETE LEVELS;
DIRECT INTERACTION CROSS-SECTIONS INCLUDED
(DWBA CALCULATIONS).
3 - 91 INELASTIC SCATTERING to CONTINUUM (GLUCS evaluation.)
3 - 102 (N,G) CROSS-SECTION BY GLUCS evaluation from 1.2 MeV
UPTO 20 MEV. FROM 1.E-5 EV UPTO 1.2 MEV THE CROSS-SEC-
TION IS PROVIDED BY RESONANCE PARAMETERS (2-151).
3 - 103 (N,P) CROSS-SECTION BY GLUCS evaluation
3 - 104 (n,d) cross-section by GLUCS evaluation
3 - 105 (n,t) cross-section from IEAF 2001
3 - 106 (n,3He) cross section from IEAF 2001
3 - 107 (N,A) CROSS-SECTIONS BY GLUCS evaluation
4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR
ELASTIC SCATTERING ONLY
up to 1.0 MeV from the resonance range evaluation
of O. Bouland (2002)
above 1.0 MeV the data from EFF 2.4 were retained
6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON AND 51CR RESIDUAL, AND ENERGY DEPENDENT YIELD
BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA
RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR
EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR
THE OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY
USED TO BENCHMARK THE TNG CALCULATIONS /10/.
6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON, ALPHA, AND 48TI RESIDUAL, AND ENERGY DEPENDENT
YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE
GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN
FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY
FOR THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE
ALPHA AND RESIDUAL). (N,XA) D-D EMISSION DATA HEAVILY
USED TO BENCHMARK THE CALCULATIONS /10/.
6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON AND 51V RESIDUAL, AND ENERGY DEPENDENT YIELD
BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA
RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR
EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR
THE OUTGOING NEUTRON). (N,XP) D-D EMISSION DATA HEAVILY
USED TO BENCHMARK THE CALCULATIONS /10/.
6-51 THROUGH 6-60 INELASTIC SCATTERING EXCITING LEVELS; EACH
SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON
AND 52CR RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR
THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED
BY DWUCK /6/ AND TNG /7,8,9,10/). COMPARISONS WITH
ANGULAR DISTRIBUTION DATA ARE GIVEN IN /10/.
6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES
SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 52CR
RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG
CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN
FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE
OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY USED
TO BENCHMARK THE TNG CALCULATIONS /10/.
6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P
AND 52V RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. (N,XP) D-D EMISSION DATA USED TO BENCHMARK
THE TNG CALCULATIONS /10/.
6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A
AND 49TI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. (N,XA) D-D EMISSION DATA USED TO BENCHMARK
THE TNG CALCULATIONS /10/.
12-51 THROUGH 12-60 BRANCHING RATIOS FOR THE LEVELS, COMPILED
BY HETRICK ET AL. /10/, ARE GIVEN.
12-102 (N,G) CAPTURE; TNG CALCULATED.
14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS
ASSUMED TO BE ISOTROPIC.
15-102 (N,G) CAPTURE; TNG CALCULATED.
33 - 1 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 2 COVARIANCES AS NC SUBSUBSECTION
33 - 3 COVARIANCES AS NC SUBSUBSECTION
33 - 4 COVARIANCES AS NC SUBSUBSECTION
33 - 16 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 28 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 28 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 51 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 52 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 53 to 57 LUMPED TO 851
33 - 58 to 60 LUMPED TO 852
33 - 91 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 102 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 103 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 104 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 105 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 106 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 107 COVARIANCE MATRIX AS NI SUBSUBSECTION
33 - 851 COVARIANCE Matrix for MT 53 to 57
33 - 852 COVARIANCE Matrix for MT 58 to 61
34 - 2 LEGENDRE COEFFICIENTS A1-A3 COVARIANCES
------ REFERENCES
/1/ M. UHL, PRIVATE COMMUNICATION.
/2/ JEF-2 EVALUATED FILE, MADE AT ENEA-BOLOGNA.
/3/ H. GRUPPELAAR, J. KOPECKY, D. NIEROP AND M.UHL,
"EVALUATION OF NEUTRON CROSS-SECTIONS AND PHOTON-PRODUC-
TION DATA FOR CR-52 AND FE-56 ISOTOPES IN THE ENERGY
RANGE 0 - 20 MEV", EFF-DOC (1990), ECN-REPORT, ECN-90.
/5/ PHYSICS DATA 13-8 (1995), Fachinformationszentr. Karlsruhe
/6/ P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF
COLORADO, UNPUBLISHED (1972).
/7/ C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND
PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR
MOMENTUM," ORNL/TM-7042 (1980) AND NSE 100, 61 (1988).
/8/ C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP
HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP.
NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y.,
MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN
NATIONAL LAB.
/9/ K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG
STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986).
/10/ D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON
-INDUCED CROSS SECTIONS FOR 52CR FROM 1 TO 20 MEV AND
COMPARISONS WITH EXPERIMENT," ORNL/TM-10417,ENDF-346 (1987).
*****************************************************************
1 451 301
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