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2.705800+4 5.743810+1 1 0 2 0
2.489000+4 1.000000+0 1 1 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 79 1
27-Co- 58MNEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 2723
-----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. *
******************************************************************
* 6-SEP-84: COMPILATION ERROR IN TOTAL CORRECTED. *
* 4-FEB-85: DATA WERE EXTENDED DOWN TO 1.0E-5 EV AFTER
* CONSULTAION WITH H.GRUPPELAAR. NEW BACKGROUND
* DATA CALCULATED.
* 21-FEB-85: Q-VALUE FOR MT=22,CORRECTED AND THRESHOLD ENERGY
* INSERTED,
* Q-VALUES FOR MT=28,102,103,107 CORRECTED
* 14-OCT-87: FOR THE SPIN OF L=0,RESONANCES HAVE BEEN RANDOMLY
ASSIGNED BY THE COMPUTER CODE RNDSPIN (GRUPPELAAR)
******************************************************************
COBALT- 58M
AUTOMATICALLY TRANSLATED INTO ENDF/B FORMAT FROM KEDAK SOURCE BY
K T O E - 3
ORIGINAL COMMENT IS:
RCN-2 EVL. FOR C0-58M (RUN N) BY H.GRUPPELAAR AND H.A.J.VAN DER K
MINIMUM ENERGY .00100 EV
MIN EN OF STATISTICAL MODEL .51000 KEV
ENERGY OF FIRST EXCITED STATE -24.9 KEV
CONTINUOUS STAT MODEL ABOVE 1.21100 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 METASTABLE TARGET*********************************
RESOLVED RESONANCE REGION UPTO ABOUT 0.5 KEV
ONLY ONE RESONANCE GIVEN. THIS WAS FITTED TO OBTAIN
AGREEMENT WITH EXPERIMENTAL VALUES FOR THERMAL
CAPTURE CROSS SECTION (SIGMA= 136 KB ) (MU73)
THE CALCULATED RESONANCE INTEGRAL IS RI=180 KB, NOT FAR FROM
THE VALUE MEASURED BY HALPERIN ET AL.(HA64).
POSSIBLY SIGMA ABSORBTION IN THE RESONANCE REGION
CONSISTS OF A CONTRIBUTION OF 75 PERCENT FOR THE (N,GAMMA)
REACTION AND OF A CONTRIBUTION OF 25 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 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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