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60-Nd-148 NEA RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 6043
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
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***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
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***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
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* JEF-2 *
* DATA WERE TAKEN FROM RCN EVALUATION *
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* 16-FEB-85: NEW BACKGROUND CROSS SECT. CALCULATED AND INSERTED
* 7-MAR-85: Q-VALUE FOR MT=102 CORRECTED
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 6-FEB-90: NEW BACKGROUND CROSS SECT. CALCULATED AND INSERTED
* 1-NOV-90: BACKGROUND CROSS SECTION IN RESOLVED RESONANCE
* REGION CORRECTED AND ADDITIONAL COMMENTS INSERTED
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* *
* MODIFICATIONS FOR JEF-2 60-ND-148 *
* *
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* *
* COOPERATION ECN-PETTEN AND NEA DATA BANK *
* H.A.J. VAN DER KAMP - ECN *
* H.GRUPPELAAR - ECN *
* I.FOREST - NEADB *
* C.NORDBORG - NEADB *
* *
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* RESOLVED RESONANCE REGION: *
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* *
* THE ORIGINAL JEF-1 EVALUATION HAS BEEN MAINTAINED. *
* *
* SPIN VALUES FOR L=1 RESONANCES HAVE BEEN REASSIGNED *
* RANDOMLY USING THE COMPUTER CODE RNDSPIN(GRUPPELAAR) *
* *
* CORRECTIONS TO AUTOMATIC CONVERSION BY KTOE HAVE BEEN *
* APPLIED. *
* *
* EL=10-5 EV, EH=7.700 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 0.662837 B *
* MT=102 SIGMA = 2.50000 B *
* MT=102 RESONANCE INTEGRAL = 19.9328 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 4.0 +- 0.5 B *
* MT=102 SIGMA = 2.5 +- 0.2 B *
* MT=102 RESONANCE INTEGRAL = 14 +- 1 B *
* *
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* REFERENCES: *
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* *
* MU81: MUGHABGHAB,S.F., M.DIVADEENAM, N.E.HOLDEN *
* NEUTRON CROSS SECTIONS VOLUME 1 *
* NEUTRON RESONANCE PARAMETERS AND THERMAL CROSS *
* SECTIONS, PART A, Z=1-60, ACADEMIC PRESS 1981 *
* *
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ORIGINAL DATA IN KEDAK FORMAT WERE TRANSLATED INTO ENDF/B
FORMAT WITH KTOE-3.
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ORIGINAL COMMENT IS:
$RCN 2.3 EVALUATION H.GRUPPELAAR ND148Z 25/07/78 $
N,P N,D N,T N,HE3 N,A ADDED (THRES-2), ABS AND TOTAL CORRECT REV
MINIMUM ENERGY .00100 EV
MIN EN OF STATISTICAL MODEL 7.75309 KEV
ENERGY OF FIRST EXCITED STATE .30170 MEV
CONTINUOUS STAT MODEL ABOVE 1.24100 MEV
HIGH ENERGY MODEL ABOVE 6.50000 MEV
MAXIMUM ENERGY 15.00000 MEV
LEVEL DENSITY PARAMETER ND148 23.60000 1/MEV
LEVEL DENSITY PARAMETER ND147 23.91000 1/MEV
*****ADJUSTED EVALUATION BASED ON STEK AND CFRMF INTEGRAL DATA***
RESOLVED ENERGY REGION UPTO 7.7 KEV
EVALUATION WITH SIGMA-2 AT 0 K, MULTILEVEL FORMULA
RESOLVED RESONANCES FROM MUSGROVE ET AL.(MU77), SUPPLEMENTED
WITH LOW-ENERGY RESONANCES AS GIVEN IN BNL-325 (MU73).
L=0 ASSIGNMENTS FROM MU77 AND THE EVALUATOR
THE NEUTRON WIDTHS ARE SLIGHTLY DIFFERENT FROM THOSE OF
MUSGROVE. THEY HAVE BEEN RECALCULATED FROM THE MEASURED
CAPTURE KERNEL AND THE ADOPTED VALUES OF J AND THE CAPTURE
WIDTH.
SMALL 1/V-COMPONENT ADDED TO CAPTURE CROSS SECTION, TO
CORRECT FOR DIFFERENCE BETWEEN CALCULATED AND MEASURED
THERMAL VALUE.
STRENGTH FUNCTION REGION UP TO 50 KEV
CAPTURE CROSS SECTIONS WITH CODE FISPRO-ECN
OTHER CROSS SECTIONS WITH CODE SASSI-ECN
S-WAVE STRENGTH FUNCTION, S0= 2.7
P-WAVE STRENGTH FUNCTION, S1= 0.58
S-WAVE CAPTURE WIDTH= 46 MV
P-WAVE CAPTURE WIDTH= 40 MV
DOBS=171 EV
HIGH ENERGY REGION
ALL CROSS SECTIONS WITH CODE SASSI-ECN
OPTICAL MODEL FROM IGARASI ET AL. (IG75)
LEVEL SCHEME OF TARGET NUCLEUS FROM NUCLEAR DATA SHEETS
(HA77)
***************** PROGRAM LINEAR (VERSION 83-1) *****************
DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.100 PER-CENT
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