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2.705800+4 5.743810+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 78 1
27-Co- 58 NEA RCOM-JUN83 SCIENTIFIC CO-ORDINATING GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 2722
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
Skeleton MF-5 MT-22,28 added
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
******************************************************************
******************************************************************
* JEF-2 *
* DATA WERE TAKEN FROM RCN-2 EVALUATION. *
******************************************************************
* 23-AUG-84: COMMENT ADDED. Q-VALUE IN MF=3,MT=91 CORRECTED.
* 4-FEB-85: DATA WERE EXTENDED DOWN TO 1.0E-5 EV AFTER
* CONSULTAION WITH H.GRUPPELAAR. NEW BACKGROUND
* CROSS SECTION CALCULATED.
* 21-FEB-85: Q-VALUES FOR MT=102 AND 103 CORRECTED
* Q-VALUE FOR MT=22,107 CORRECTED AND CORRESPONDING
* THRESHOLD ENERGY POINT INSERTED
* 14-OCT-87: FOR THE SPIN OF L=0 RESONANCES HAVE BEEN RANDOMLY
ASSIGNED BY THE COMPUTER CODE RNDSPIN (GRUPPELAAR)
******************************************************************
COBALT-58
AUTOMATICALLY TRANSLATED INTO ENDF/B FORMAT FROM KEDAK SOURCE BY
K T O E - 3
ORIGINAL COMMENT IS:
RCN-2 EVL. FOR CO-58G BY H.GRUPPELAAR AND H.A.J.VAN DER KAMP (29/
MINIMUM ENERGY .00100 EV
MIN EN OF STATISTICAL MODEL .60000 KEV
ENERGY OF FIRST EXCITED STATE 24.90000 KEV
CONTINUOUS STAT MODEL ABOVE 1.23600 MEV
HIGH ENERGY MODEL ABOVE 6.50000 MEV
MAXIMUM ENERGY 20.00000 MEV
LEVEL DENSITY PARAMETER CO058 6.50000 1/MEV
LEVEL DENSITY PARAMETER CO057 6.00000 1/MEV
*****CROSS SECTIONS FOR NUCLIDES IN COOLING CIRCUIT OF LMFBR*****
*****COBALT-58 GROUND STATE TARGET*******************************
RESOLVED RESONANCE REGION UPTO ABOUT 0.5 KEV
ONLY ONE RESONANCE GIVEN. THIS WAS FITTED TO OBTAIN
REASONABLE AGREEMENT WITH EXPERIMENTAL VALUES FOR THERMAL
CAPTURE CROSS SECTION (SIGMA= 1880 B.) AND RESONANCE
INTEGRAL( RI= 6890 B.), VALUES GIVEN IN BNL-325
POSSIBLY SIGMA ABSORBTION IN THE RESONANCE REGION
CONSISTS OF A CONTRIBUTION 0F 10 PERCENT FOR THE (N,GAMMA)
REACTION AND A CONTRIBUTION OF 90 PERCENT FOR THE (N,P)
REACTION.
OPTICAL MODEL AND STATISTICAL MODELS ABOVE 0.5 KEV
TOTAL, CAPTURE AND NEUTRON SCATTERING CROSS SECTIONS WITH
CODE SASSI-ECN.
NEUTRON OPTICAL MODEL FROM FORT (FO79).
DOBS=1.17 KEV FROM SYSTEMATICS.
GUESSED AVERAGE CAPTURE WIDTH= 0.5 EV.
CHARGED-PARTICLE EMISSION CROSS SECTIONS FROM CODES CERBERO
AND ERINNI.
THE (N,D) CROSS SECTION CALCULATED WITH CODE THRES-2
WITH RENORMALIZATION TO SYSTEMATICS.
(N,P) CROSS SECTION IS IMPORTANT DOWN TO THERMAL
ENERGIES.
LEVEL-DENSITY PARAMETERS MOSTLY FROM SYSTEMATICS.
LEVEL SCHEMES FROM NUCLEAR DATA SHEETS AND OWN EVALUATION.
NO EXPERIMENTAL CROSS SECTIONS AVAILABLE FOR COMPARISONS.
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