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60-Nd-146 NEA RCOM-JUL83 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 6037
-----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-3 EVALUATION (MAT=4606). *
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* 16-FEB-85: NEW BACKGROUND CROSS SECT. CALCULATED AND INSERTED
* 7-MAR-85: Q-VALUES FOR MT=102,107 CORRECTED
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 1-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-146 *
* *
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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. *
* *
* THE RESONANCE SPINS OF THE L=1 RESONANCES HAVE BEEN *
* REASSIGNED RANDOMLY USING THE COMPUTER CODE RNDSPIN *
* (GRUPPELAAR). *
* *
* CORRECTIONS TO THE AUTOMATIC CONNVERSION BY KTOE HAVE *
* BEEN APPLIED. *
* *
* EL=10-5 EV, EH=10.00 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 4.36628 B *
* MT=102 SIGMA = 1.40000 B *
* MT=102 RESONANCE INTEGRAL = 2.82537 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 9.6 +- 0.4 B *
* MT=102 SIGMA = 1.4 +- 0.1 B *
* MT=102 RESONANCE INTEGRAL = 3.2 +- 0.5 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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EVAL. FOR: NEODYMIUM - 146 DISTR: JUL 78
ORIGINAL COMMENT IS:
$RCN 3 EVALUATION H.GRUPPELAAR ND146Z 24/07/78 $
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 9.95189 KEV
ENERGY OF FIRST EXCITED STATE .45370 MEV
CONTINUOUS STAT MODEL ABOVE 1.83720 MEV
HIGH ENERGY MODEL ABOVE 6.50000 MEV
MAXIMUM ENERGY 15.00000 MEV
LEVEL DENSITY PARAMETER ND146 20.25000 1/MEV
LEVEL DENSITY PARAMETER ND145 20.42000 1/MEV
*****ADJUSTED EVALUATION BASED ON STEK AND CFRMF INTEGRAL DATA***
*****OTHER DIFFERENCE: S0 ACCORDING TO MUSGROVE ET AL. (MU77)
RESOLVED ENERGY REGION UPTO 10 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 MUSG
THEY HAVE BEEN RECALCULATED FROM THE MEASURED CAPTURE KERNEL
AND THE ADOPTED VALUES OF J AND THE CAPTURE WIDTH.
A NEGATIVE RESONANCE HAS BEEN ASSUMED TO FIT THE CAPTURE
CROSS SECTION AT 0.0253 EV (MU73).
STRENGTH FUNCTION REGION UPTO 50 KEV
CAPTURE CROSS SECTIONS WITH CODE FISPRO-ECN
OTHER CROSS SECTIONS WITH CODE SASSI-ECN
S-WAVE STRENGTH FUNCTION, S0=3.7 (MU77)
P-WAVE STRENGTH FUNCTION, S1=0.95
S-WAVE CAPTURE WIDTH = 51 MV
P-WAVE CAPTURE WIDTH = 40 MV
DOBS=278 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 (BU7
***************** PROGRAM LINEAR (VERSION 83-1) *****************
DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.100 PER-CENT
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