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60-Nd-144 NEA RCOM-JUL83 H.GRUPPELAAR,E.MENAPACE
JEF/DOC-30 DIST-JAN09 20090105
----JEFF-311 MATERIAL 6031
-----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=4604). *
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* 16-FEB-85: NEW BACKGROUND CROSS SECT. CALCULATED AND INSERTED
* 7-MAR-85: Q-VALUES FOR MT=102,107 CORRECTED
* 16-OCT-86: RESONANCE PARAMETER SECTION UPDATED USING DATA *
* FROM THE 4TH ED. OF BNL-325, AND SPIN OF L=1 *
* RESONANCES HAVE BEEN RANDOMLY ASSIGNED BY THE *
* COMPUTER CODE RNDSPIN (H. GRUPPELAAR). *
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
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* *
* MODIFICATIONS FOR JEF-2 60-ND-144 *
* *
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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 SPINS OF THE L=1 RESONANCES HAVE BEEN REASSIGNED *
* USING THE COMPUTER CODE RNDSPIN(GRUPPELAAR). *
* *
* EL=10-5 EV, EH=12.00 KEV. *
* *
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* THERMAL VALUES (2200M/S): *
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* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 0.259385 B *
* MT=102 SIGMA = 3.58250 B *
* MT=102 RESONANCE INTEGRAL = 4.16218 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 1.0 +- 0.2 B *
* MT=102 SIGMA = 3.6 +- 0.3 B *
* MT=102 RESONANCE INTEGRAL = NOT AVAILABLE *
* *
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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 - 144 DISTR: JUL 78
ORIGINAL COMMENT IS:
$RCN 3 EVALUATION H.GRUPPELAAR ND144X 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 11.89890 KEV
ENERGY OF FIRST EXCITED STATE .69650 MEV
CONTINUOUS STAT MODEL ABOVE 2.29510 MEV
HIGH ENERGY MODEL ABOVE 6.50000 MEV
MAXIMUM ENERGY 15.00000 MEV
LEVEL DENSITY PARAMETER ND144 17.60000 1/MEV
LEVEL DENSITY PARAMETER ND143 18.80000 1/MEV
*****ADJUSTED EVALUATION BASED ON STEK INTEGRAL DATA*****
*****OTHER DIFFERENCE: S0 ACCORDING TO MUSGROVE ET AL. (MU77)
RESOLVED ENERGY REGION UPTO 12 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
SOME NEUTRON WIDTHS ARE DIFFERENT FROM THOSE IN MU77,
THEY HAVE BEEN RECALCULATED FROM CAPTURE KERNEL AND
ADOPTED VALUES FOR J AND 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 SASSI-ECN
OTHER CROSS SECTIONS WITH CODE SASSI-ECN
S-WAVE STRENGTH FUNCTION, S0=3.9 (MU77)
P-WAVE STRENGTH FUNCTION, S1=0.9
S-WAVE GAMMA WIDTH = 47 MV
P-WAVE GAMMA WIDTH = 41 MV
DOBS= 477 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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