3.100000+4 6.912110+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 0 170 1
31-Ga- 0 KHI EVAL-MAR94 T.WATANABE
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 3100
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JENDL-3.2 (DIST-OCT96)
JEF-2.2 (MF12-MF15)
******************************************************************
HISTORY
94-3 NEW EVALUATION WAS CONSTRUCTED FROM ISOTOPES DATA
MF=1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS
RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA (BELOW 5.9KEV.)
THE DATA WERE CONSTRUCTED FROM THE EVALUATED RESONANCE
PARAMETERS FOR GA-69 AND GA-71, CONSIDERING THEIR
ABUNDANCES/1/.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)
2200 M/S RES. INTEG.
TOTAL 9.8 -
ELASTIC 7.0 -
CAPTURE 2.8 23.8
MF=3 NEUTRON CROSS SECTIONS
BELOW 5.9 KEV, RESONANCE PARAMETERS WERE GIVEN.
ABOVE 5.6 KEV, THE TOTAL, ELASTIC AND INELASTIC SCATTERING, AND
CAPTURE PARTIAL CROSS SECTION WERE GIVEN USING EACH ISOTOPES
DATA CALCULATED WITH CASTHY PROGRAM/2/.
MT=16,22,28,32,102,103,104,105,106,107,111,251
(N,2N),(N,NA),(N,NP),(N,ND),(N,P),(N,D),(N,T),(N,HE-3),
(N,A),(N,2P),MU-BAR
WERE CONSTRUCTED FROM EACH GA ISOTOPE DATA CONSIDERING
ABUNDANCES.
CROSS SECTIONS FOR EACH ISOTOPE WERE EVALUATED USING CASTHY
AND MADIFIED EGNASH-2/3/ PROGRAMM.
NEUTRON OPTICAL POTENTIAL PARAMETERS USED WERE AS FOLLOWS.
DEPTH (MEV) R*A**(1/3) DIFFUSENESS(FM)
---------------------- ------------ ---------------
V = 49.42-0.5867E , R0 = 1.293 , A0 = 0.415
WS = 5.381+0.4117E , RS = 1.308 , AS = 0.456
WSO= 8.552 , RSO= 1.583 , ASO= 0.648
THE LEVEL SCHEME WAS ADOPTED FROM ENSDF FILE.
NO. ENERGY(MEV) SPIN-PARITY ISOTOPE
GR. 0.0000 3/2 - GA-69,-71
1 0.3187 1/2 - GA-69
2 0.3900 1/2 - GA-71
3 0.4872 5/2 - GA-71
4 0.5116 3/2 - GA-71
5 0.5741 5/2 - GA-69
6 0.7140 11/2 - GA-71
7 0.8720 3/2 - GA-69
8 0.9103 3/2 - GA-71
9 0.9648 5/2 - GA-71
10 1.0285 1/2 - GA-69
11 1.1068 5/2 - GA-69
1.1074 7/2 - GA-71
1.1093 1/2 - GA-71
12 1.1340 7/2 - GA-69
13 1.3366 7/2 - GA-69
14 1.3952 7/2 - GA-71
15 1.4759 5/2 - GA-71
16 1.4880 7/2 - GA-69
1.4937 9/2 + GA-71
1.4986 5/2 - GA-71
17 1.5259 3/2 - GA-69
18 1.6316 3/2 - GA-71
19 1.7022 1/2 + GA-71
20 1.7198 5/2 - GA-71
21 1.7237 5/2 - GA-69
22 1.7524 3/2 - GA-71
1.7648 9/2 - GA-69
23 1.8916 3/2 - GA-69
1.9040 5/2 - GA-71
24 1.9242 7/2 - GA-69
25 1.9410 3/2 + GA-71
26 1.9724 9/2 + GA-69
1.9731 1/2 - GA-69
27 2.0076 3/2 - GA-69
1.9950 5/2 - GA-71
28 2.0238 5/2 - GA-69
29 2.0452 5/2 - GA-69
30 2.0640 1/2 - GA-71
31 2.1342 5/2 - GA-71
32 2.1980 13/2 - GA-69
2.1913 5/2 - GA-71
2.2060 5/2 - GA-71
33 2.2193 1/2 + GA-69
34 2.2510 1/2 - GA-69
2.2472 7/2 + GA-71
35 2.2944 1/2 - GA-71
36 2.3195 7/2 + GA-69
2.3273 1/2 - GA-71
37 2.3533 5/2 - GA-69
38 2.4233 13/2 - GA-69
2.4288 5/2 - GA-69
LEVELS ABOVE 2.33 MEV WERE ASSUMED TO BE OVERLAPPING.
PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GIRBERT-
CAMERON WERE EVALUATED.
SPIN CUT-OFF PARAMETER C1 WAS TAKEN AS 0.146.
GA- 69 GA- 70 GA- 71 GA-72
---------------------------------------
A (MEV) 11.340 11.590 13.000 12.900
SPIN CUT-OFF PARAM. 8.271 8.442 9.026 9.075
PAIRING ENERGY (MEV) 1.500 0.0 1.430 0.0
NORMALIZATION FACTOR 1481.60 1536.20 1747.70 1758.60
E-JOINT (MEV) 6.924 4.221 6.326 4.961
MF=4 MT=2,16,22,28,32,51-88,91
(N,2N),(N,NA),(N,NP),(N,ND) AND ELASTIC AND INELASTIC SCATTERING
ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
WERE CONSTRUCTED FROM EACH GA ISOTOPE DATA CONSIDERING
ABUNDANCES.
MF=5 MT=16,22,28,32,91
(N,2N),(N,NA),(N,NP),(N,ND) AND CONTINUM INELASTIC SCATTERING
ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
WERE CONSTRUCTED FROM EACH GA ISOTOPE DATA CONSIDERING
ABUNDANCES.
REFERENCES
1)C.M.LEDERER ET.AL. TABLE OF ISOTOPES 7TH ED.(1978)
JOHN WILEY & SONS INC.
2)S.IGARASHI,T.FUKAHORI JAERI-1321 (1991)
3)N.YAMAMURO JAERI-M 90-006(1991)
******************************************************************
Relevant comments from EFF-2.4
------------------------------
PHOTON PRODUCTION FROM (N,GAMMA) REACTIONS
THE SPECTRUM OF PHOTONS FROM THE NEUTRON CAPTURE PROCESS AT
THERMAL NEUTRON ENERGIES WAS TAKEN FROM THE MEASUREMENTS OF
ORPHAN ET EL., GA-10248(1970). THIS SPECTRUM WAS ASSUMED TO
APPLY AT ALL INCIDENT NEUTRON ENERGIES UP TO 20 MEV, BUT THE
PHOTON MULTIPLICITY WAS ADJUSTED SO AS TO CONSERVE THE TOTAL
ENERGY OF THE REACTION.
(N,X GAMMA) CROSS SECTION
THERE ARE NO EXPERIMENTAL (N,X GAMMA) DATA. THE EVALATED
DATA WERE CALCULATED WITH THE NXGAMEL CODE, USEING THE SYSTEM-
ATICS DEVELOPED BY PERKINS ET AL., NUCL. SCI. ENG. 57, 1(1975).
THE EVALUATED (N,X GAMMA) CROSS SECTION IS REPRESENTED AS A
CONTINUUM THAT HAS A THRESHOLD AT 0.4 MEV.
SPECTRA OF PHOTONS FROM THE (N,X GAMMA) PROCESS
THE PHOTON ANGULAR DISTRIBUTIONS WERE ASSUMED TO BE
ISITROPIC. THE PHOTON ENERGY DISTRIBUTIONS WERE OBTAINED FROM
THE SYSTEMATICS OF PERKINS ET AL., CITED ABOVE.
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