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2.806000+4 5.941595+1 1 0 2 0
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 0 315 1
28-Ni- 60 IRK-IJS EVAL-JAN00 EUROPEAN JOINT COLLABORATION
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 2831
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- EFF-3.0 (DIST-JAN00 REV0-MAR00)
Restore corrupted Es in MF12,MT50 series (A.Trkov, May 2003)
******************************************************************
Authors and Responsibilities:
S.Tagesen, H.Vonach and A.Wallner, I.R.K.:
- Complete evaluation of the cross sections including covariance
matrices by generalized least squares cross section update
code GLUCS (9, 10) in the energy range from 450 keV to 20 MeV.
The total cross section is evaluated in broad energy bins.
A.Trkov, I.J.S.:
- Data reduction of the Brusegan et.al. data.
- Final assembly of the file.
- Implementation of the resonance fluctuations on the smooth
newly evaluated cross sections.
- Preliminary data verification and benchmarking.
Evaluation Details:
The Oak Ridge Ni-60 ENDF/B-VI Revision 1 evaluation (MAT 2831)
by Larson et.al. was the chosen starter file. All neutron
cross sections above 500 keV were updated and include
covariance data. In the energy range between 500 keV and 6 MeV
the fluctuations in the total cross section measured by Brusegan
et.al. (11) were superimposed on the smooth total and inelastic
cross sections evaluated by Tagesen et.al. The following data
sets were selected as "priors":
MT1 EFF-2
MT16 EFF-2
MT22 ENDF-B/VI
MT28 EFF-2
MT51 EFF-2
MT52-53 EFF-2
MT54-55 EFF-2
MT56-61 EFF-2
MT91 EFF-2
MT102 EFF-2
MT103 evaluation Badikov (12)
MT104 ENDF-B/VI
MT105 JENDL-3
MT106 JENDL-3
MT107 EFF-2
The Evaluation was performed in three steps:
step 1: Individual excitation functions updated with new experi-
mental data points
MT1 In the energy range 450 keV to 4 MeV
exclusively isotopic data were used
6 data sets, 58 datapoints
EXFOR #: 10124(Stoler), 10879(Smith), 11601(Farrel),
22314(Brusegan), 40614(Fedorov), Larson
In the energy range above 4 MeV also all
available exp. data from nat. Ni were included
23 data sets, 174 datapoints
EXFOR #: 10047(Foster), 10225 023(Green), 10225 024
(Green), 10342 002(Perey), 10342 003(Perey),
10416(Schwartz), 10593(Guenther),10823(Smith)
11056(Coon), 11057(Goodman), 11108(Peterson)
11155(Brathenahl), 12882(Larson), 20012(Cier-
jacks), 20480 015(Cabe), 21122(McCallum)
30037(Mazari), 30141(Angeli), 31486(Poli-
croniades), 40559(Tutubalin), 68023(Tsukada)
MT51 8 data sets, 66 datapoints
EXFOR #: 10037(Boschung), 10146(Rodgers), 10487(Perey)
12930(Guss), 10113(Kinney), 10879(Smith-79a)
10879(Smith-79b), 22128(Olsson)
MT52-53 5 data sets, 41 datapoints
EXFOR #: 10037(Boschung), 10852(Traiforos)
10113(Kinney), 10879(Smith-79a), 10487(Perey)
MT54-55 5 data sets, 30 datapoints
EXFOR #: 10037(Boschung), 10852(Traiforos)
10113(Kinney), 10879(Smith-79a), 10487(Perey)
MT56-61 1 data set, 1 datapoint
EXFOR #: 10487(Perey)
MT104 2 data sets, 2 datapoints
EXFOR #: 10827(Grimes), 12999(Graham)
MT105 1 data set, 1 datapoint
EXFOR #: 20699(Qaim)
step 2: combined evaluation of alpha and proton production xsec.
MT22+107 6 data sets, 35 datapoints
EXFOR #: 10827(Grimes), 13598(Haight96), 10933(Kneff)
21920(Fischer), Haight97, 12999(Graham)
MT28+103 1 data set, 1 datapoint
EXFOR #: 10827(Grimes)
step 3: combined evaluation of all reactions with redundant data
MT2 7 data sets, 26 datapoints
EXFOR #: 10037(Boschung), 10113(Kinney), 10487(Perey)
12930(Guss), 10879(Smith-79a)
20019(Holmquist), 22048(Olson)
MT3 4 data sets, 7 datapoints
EXFOR #: 11216(Beyster), 11217(Taylor), 11220(Beyster)
1 eval.pt. (Pavlik)
MT4 6 data sets, 80 datapoints
EXFOR #: 10852(Traiforos), 10439(Tessler), Larson
1 eval.pt. (Pavlik), 20744(Voss), 20905
(Towle)
MT91 1 data set, 1 data point
derived by spectrum integration 5 - 11 MeV
overall Chisq./deg.of freedom 1.238
A detailed description including literature references will be
given in an IAEA(NDS) - Report, published by the IAEA.
Resonance Fluctuations in the Cross Sections:
The cross sections below 500 keV are not affected by the re-
evaluation process. Above this energy, the broad bin average
total cross section crresponds to the Tagesen et.al. evaluation
and the shape is taken from the high resolution measurements by
Brusegan et.al. (11).
The Brusegan data are smoothed to piecewise linear form to
remove the statistical fluctuations in the measurements and to
reduce the number of points. The broad bin average values
are calculated. The bins correspond to those used in the
re-evaluation process. A broad bin smooth cross section curve
is generated, conserving the bin average values. Fluctuations
modulating function is defined as the ratio of the Brusegan
smoothed and the broad bin smoothed cross section. This
modulating function is applied on the re-evaluated broad bin
smooth total cross section and the inelastic cross sections.
Other Data:
The remaining comments are taken over from the starter file,
except for the sections referring to the data, which have been
superseeded. Modified sections are identified by the use of
lower case characters.
============================================================
THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE
DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1)
AND THE HAUSER-FESHBACH CODE TNG (2,3,4). THE TNG CODE PROVIDES
ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE
COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL
REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE
CONTENTS OF THIS EVALUATION AND EXTENSIVE COMPARISONS OF
CALCULATIONS WITH EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5).
----- DESCRIPTION OF FILES
(MF-MT)
1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.
2-151 RESONANCE PARAMETERS -- TAKEN FROM REF (6). THE NEGATIVE
ENERGY RESONANCES WERE ADJUSTED BY THE AUTHOR, C. M. PEREY
TO GIVE THE PROPER THERMAL SCATTERING AND CAPTURE. USING
THESE MODIFIED RESULTS, NO BACKGROUND IS REQUIRED IN 3/1
IE, THE TOTAL, SCATTERING AND CAPTURE IS GIVEN COMPLETELY
BY THE RESONANCE PARAMETERS FROM 1.E-5 EV TO 450 KEV.
RESONANCE PARAMETERS ARE FROM A REICH-MOORE ANALYSIS WITH
THE CODE SAMMY (REF 7).
THUS, THE THERMAL CROSS SECTIONS ARE GIVEN BY THE
RESONANCE PARAMETERS AND HAVE VALUES: TOTAL 3.9 B,
ELASTIC SCATTERING 0.98 B, AND CAPTURE 2.92 B.
NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION
OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE
PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON
A FINER ENERGY GRID THAN GIVEN IN 4/2.
3-1 TOTAL CROSS SECTION -- FROM 450 KEV TO 500 KEV THE DATA
OF REF (8) WERE USED.
Above 500 keV the data are re-evaluated as described
above.
3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY
SUBTRACTING THE NONELASTIC FROM THE TOTAL
3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22,
3-28, 3-102, 3-103, 3-104, AND 3-107.
3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, ..
.., 3-61, AND 3-91
3-16 (n,2n) cross sections were re-evaluated.
3-22 (n,na) cross sections were re-evaluated.
3-28 (n,np) cross sections were re-evaluated.
3-51 to 3-61 inelastic scattering exciting levels was
re-evaluated. Fluctuations of the total cross section
were imposed.
3-91 inelastic scattering exciting the continuum was
re-evaluated. Fluctuations of the total cross section
were imposed.
3-102 (N,G) CAPTURE CROSS SECTION TAKEN FROM RESONANCE PARAMETER
FROM 1.E-5 EV TO 450 KEV. TNG CALCULATIONS WERE
NORMALIZED TO THE AVERAGED CROSS SECTION OBTAINED FROM THE
RESONANCE PARAMETERS FROM 100-450 KEV. THESE NORMALIZED
TNG RESULTS WERE USED FROM 450 KEV TO 500 KEV.
Above 500 keV the cross sections were re-evaluated.
3-103 (n,p) cross sections were re-evaluated.
3-104 (n,d) cross sections were re-evaluated.
3-107 (n,a) cross sections were re-evaluated.
4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR
ELASTIC SCATTERING ARE FROM ENDF/B-V. AGREE WELL WITH DATA
IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY
THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE
PARAMETERS IN 2/151.
6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON AND 59NI 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). COMPARES WELL WITH N EMISSION DATA
WHEN COMBINED WITH N FROM 6/22, 6/28 AND 6/91.
6-22 (N,NA)+(N,AN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON, ALPHA, AND 56FE 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).
6-28 (N,NP)+(N,PN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON, P, AND 59CO 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).
6-51 THROUGH 6-61 INELASTIC SCATTERING EXCITING LEVELS; EACH
SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON
AND 60NI RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR
THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED
BY DWUCK (1) AND TNG (2,3,4,5)), COMPARED WITH DATA IN (5)
6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES
SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 60NI
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).
6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P
AND 60CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. COMPARES WELL WITH P EMISSION DATA WHEN COMBINED
WITH 6/28.
6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A
AND 57FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. COMPARES WELL WITH A EMISSION DATA WHEN COMBINED
WITH 6/22.
12-51 THROUGH 12-61 BRANCHING RATIOS FOR THE LEVELS, COMPILED
BY HETRICK ET AL. (5), ARE GIVEN.
12-102 (N,G) CAPTURE; MULTIPLICITIES WERE 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
--------------------------------------------------------------
UNCERTAINTY FILES
ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS
REQUIRED BY ENDF/B-VI FORMATS
For all evaluated reactions full covariance matrices are
given as calculated by the bayesian evaluation update code
GLUCS. This includes full inter-reaction covariances.
33-1 TOTAL UNCERTAINTIES estimated from 1E-5 TO 450 keV, full
covariances from GLUCS from 450 keV to 20 MeV.
33-2 DERIVED FROM 1E-5 TO 20 MEV
33-3 DERIVED FROM 1E-5 to 20 MeV.
33-4 DERIVED FROM THRESHOLD TO 20 MEV.
33-16 (N,2N) covariances from GLUCS.
33-22 (N,NA) covariances from GLUCS.
33-28 (N,NP) covariances from GLUCS.
33-51 inelastic scattering covariances from GLUCS
33-52-53 inelastic scattering covariances lumped into MT851
33-54-55 inelastic scattering covariances lumped into MT852
33-56-61 inelastic scattering covariances lumped into MT853
33-91 inelastic scattering covariances from GLUCS
33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM 1E-5 to 550 keV,
covariances from GLUCS from 550 keV TO 20 MEV.
33-103 (N,P) covariances from GLUCS.
33-104 (N,D) covariances from GLUCS.
33-105 (n,t) covariances from GLUCS.
33-106 (n,3He) covariances from GLUCS.
33-107 (N,A) covariances from GLUCS.
34- 2 LEGENDRE COEFFICIENTS A1-A3 COVARIANCES FROM EFF-2.4
REFERENCES:
(1) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF
COLORADO, UNPUBLISHED (1972).
(2) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND
PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR
MOMENTUM," ORNL/TM-7042 (1980).
(3) 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.
(4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG
STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986).
(5) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON
-INDUCED CROSS SECTIONS FOR 58,60NI FROM 1 TO 20 MEV AND
COMPARISONS WITH EXPERIMENT," ORNL/TM-10219,ENDF-344 (1987).
(6) C.M. PEREY, J.A. HARVEY, R.L. MACKLIN, F.G. PEREY AND R.R.
WINTERS, PHYS. REV. C27, 2556 (1983)
(7) N.M. LARSON AND F.G. PEREY,"USERS GUIDE FOR SAMMY:A COMPUTER
MODEL FOR MULTILEVEL R-MATRIX FITS TO NEUTRON DATA USING
BAYES' EQUATIONS, ORNL/TM-7485, OAK RIDGE NATIONAL LAB, 1980;
"UPDATED USERS' GUIDE FOR SAMMY", ORNL/TM-9179, 1984,
ORNL/TM-9179/R1, 1985, AND ORNL/TM-9179/R2, 1988.
(8) J.A. HARVEY, ORELA, 80-M NE110 TA TARGET DATA, SENT TO NNDC
(9) D.M. HETRICK AND C.Y. FU, "GLUCS: A GENERALIZED LEAST SQUARES
PROGRAM FOR UPDATING CROSS SECTION EVALUATIONS WITH
CORRELATED DATA SETS," ORNL/TM-7341, ENDF-303 (OCT,1980).
(10) S. TAGESEN and D.M. HETRICK, "Enhancements to the Generalized
Least-Squares Cross-Section Evaluation Code GLUCS", Proc.Int.
Conf. on Nuclear Data for Science and Technology, Gatlinburg
Tennessee, May 9 - 13, 1994, p 589.
(11) A.Brusegan, G.Rohr, R.Shelley, E.Macavero, C.van der Voorst,
F.Poortmans, I.Mewissen, G.Vanpraet: Very High Resolution
Transmission Measurements and Resonance Parameters of Ni-58
and Ni-60, EXFOR entry 22314001.
(12) S. Badikov, S. Tagesen and H. Vonach, Physics Data 13-9,
Fachinformationszentrum Karlsruhe, 1996
1 451 320
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