3.908900+4 8.814200+1 1 0 2 0
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 81 1
39-Y - 89 ANL,LLNL EVAL-JAN86 R.HOWERTON(LLNL),A.SMITH(ANL)
AND D.SMITH(ANL). DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 3925
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
******************************************************************
* JEF-2 *
* DATA WERE RECEIVED FROM A.B. SMITH. *
******************************************************************
* 1-NOV-90: RESONANCE PARAMETERS BY ECN ADDED AND ADDITIONAL
* COMMENTS INSERTED
******************************************************************
****************************************************************
* *
* MODIFICATIONS FOR JEF-2 39-Y - 89 *
* *
****************************************************************
* *
* COOPERATION ECN-PETTEN AND NEA DATA BANK *
* H.A.J. VAN DER KAMP - ECN *
* H.GRUPPELAAR - ECN *
* I.FOREST - NEADB *
* C.NORDBORG - NEADB *
* *
****************************************************************
* RESOLVED RESONANCE REGION: *
****************************************************************
* *
* THE EXISTING JEF-1 EVALUATION WAS REPLACED BY AN *
* EVALUATION OF HOWERTON ET AL.(HO86). IN THIS EVALUATION *
* RESOLVED RESONANCE PARAMETERS WERE REPLACED BY DATA FROM *
* MOST RECENT BROOKHAVEN COMPILATION(MU81). *
* *
* FOR THOSE RESONANCES FOR WHICH GN AND GG VALUES ARE *
* UNKNOWN, AN AVERAGE VALUE FOR GG HAS BEEN ASSUMED AND *
* GN WAS DERIVED FROM THIS AVERAGE VALUE AND THE *
* CAPTURE AREA AS GIVEN IN MU81. *
* *
* EL=10-5 EV, EH= 150.0 KEV *
* *
****************************************************************
* THERMAL VALUES (2200M/S): *
****************************************************************
* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 7.70677 B *
* MT=102 SIGMA = 1.28500 B *
* MT=102 RESONANCE INTEGRAL = 0.919331 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 7.67 +- 0.06 B *
* MT=102 SIGMA = 1.28 +- 0.02 B *
* MT=102 RESONANCE INTEGRAL = 1.0 +- 0.1 B *
* *
****************************************************************
* REFERENCES: *
****************************************************************
* *
* HO86: HOWERTON,R., A.SMITH, D.SMITH *
* ANL/NDM-94(1986) *
* *
* 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 *
* *
****************************************************************
ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC
* * * * * * *
FULLY DOCUMENTED IN ANL/NDM-94(1986).
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