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27-Co- 58MNEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP DIST-JAN09 20090105 ----JEFF-311 MATERIAL 2723 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** 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.Back |