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4.710700+4 1.059870+2 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 0 103 1
47-Ag-107 NEA RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 4725
-----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 TAKEN FROM ENDF/B-V(MAT=1371). *
******************************************************************
* 28-NOV-86: RESONANCE PARAMETER SECTION UPDATED USING DATA *
* FROM THE 4TH ED. OF BNL-325. *
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
* 1-NOV-90: ADDITIONAL COMMENTS INSERTED
******************************************************************
****************************************************************
* *
* MODIFICATIONS FOR JEF-2 47-AG-107 *
* *
****************************************************************
* *
* 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: *
****************************************************************
* *
* RESOLVED RESONANCE PARAMETERS WERE REPLACED BY DATA FROM *
* MOST RECENT BROOKHAVEN COMPILATION(MU81). *
* *
* EL=10-5 EV, EH=1.0579 KEV. *
* *
****************************************************************
* THERMAL VALUES (2200M/S): *
****************************************************************
* *
* CALCULATED VALUES: *
* MT=2 SIGMA = 7.53393 B *
* MT=102 SIGMA = 37.6077 B *
* MT=102 RESONANCE INTEGRAL = 107.421 B *
* *
* EXPERIMENTAL VALUES: *
* MT=2 SIGMA = 7.44 +- 0.09 B *
* MT=102 SIGMA = 37.6 +- 1.2 B *
* MT=102 RESONANCE INTEGRAL = 100 +- 5 B *
* *
****************************************************************
* REFERENCES: *
****************************************************************
* *
* 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 *
* *
****************************************************************
HEDL,BNL EVAL-NOV78 SCHENTER,BHAT,PRINCE,JOHNSON,ETAL
DIST-JUN79 790611
HEDL EVAL-NOV78 SCHENTER,JOHNSON (FAST CAPTURE)
HEDL EVAL-NOV78 MANN,SCHMITTROTH (FAST CAPTURE)
BNL EVAL-OCT71 BHAT,PRINCE (ENDF/B-IV)
DATA USED
2200 M/SEC CAPTURE 36.85B BASED ON R.B.TATTERSALL ET.AL JOUR NUCL
ENERGY VOL12,32,1960
RESOLVED RESONANCE PARAMETERS BNL-325(2ND EDN) AND MURADYAN ET.
AL. 66PARIS,VOLI,79,66
KEV CAPTURE HEDL REEVALUATION 11/78 1 KEV TO 20 MEV
MEV TOTAL CROSS-SECTION AG(NAT) IN BNL-325(2ND EDN)
(N,2N) DATA 1.523B B.MINETTI AND A.PASQUARELLI NUC.PHYS.VOLA118,
449,1968.
(N,P),(N,ALPHA) ADJUSTED TO THE SAME NORMALIZATION AS AG-109 DATA
NUCLEAR MODEL CALCULATIONS
OPTICAL MODEL PARAMETERS WILMORE-HODGSON PARAMETERS P.E.HODGSON
ANN.REV.NUCL.SC.VOL17,1,1967. R0=1.26FM
CODES USED
1.ABACUS-NEARREX.P.MOLDAUER(PRIVATE COMMUNICATION)
TOTAL AND SHAPE-ELASTIC CROSS-SECTIONS
2.COMMNUC(AI-AEC-12931)C.DUNFORD COMPOUND NUCLEUS REAC
TION CROSS-SECTIONS
3.THRESH(TO BE PUBLISHED)S.PEARLSTEIN.(N,2N),(N,P),
(N,ALPHA) CROSS-SECTIONS. THRESHOLD ENERGIES BASED
ON LATEST DATA OF WAPSTRA AND GOVE USED IN
UCRL-50400 VOL9 BY R.J.HOWERTON
4.CHAD(NAA-SR-11231)R.F.BERLAND ANGULAR DISTRIBUTION
DATA
NUCLEAR TEMPERATURE CALCULATIONS BASED ON GILBERT AND CAMERON
CAN.JOUR.PHYS.VOL43,1446,1965
1 451 108
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