47-Ag- 0
47-AG- 0 JAERI EVAL-MAR87 LIU T.J.,T.NAKAGAWA,K.SHIBATA
DIST-SEP89 REV2-FEB94
----JENDL-3.2 MATERIAL 4700
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION FOR JENDL-3/1/
87-07 COMPILED BY K.SHIBATA
94-02 JENDL-3.2 WAS MADE BY JNDC FPND W.G.
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) RESOLVED RESONANCE PARAMETERS
(3,2), (3,3), (3,4), (3,51-62), (3,64-71), (3,73-79)
CURVES OF INELASTIC SCATTERING CROSS SECTIONS
WERE SMOOTHED BY ADDING INTERPOLATED VALUES AT
SEVERAL ENERGY POINTS.
(3,102) ONLY Q-VALUE WAS MODIFIED.
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS
THIS FILE WAS MADE OF AG-107 AND AG-109 DATA.
RESOLVED RESONANCE PARAMETERS (BELOW 7.0095KEV)
RESOLVED RESONANCE PARAMETERS (BELOW 7.0095 KEV) OF
JENDL-3.1 ARE THE SAME AS THOSE OF JENDL-2, WHICH WERE MADE BY
NAKAJIMA /2/ ON THE BASIS OF EXPERIMENTAL DATA BY MOXON AND
RAE /3/, GARG ET AL./4/, ASGHAR ET AL./5/, PATTENDEN /6/,
MURADJAN AND ADAMCHUK /7/, DE BARROS ET AL./8/, PATTENDEN AND
JOLLY /9/, MACKLIN /10/ AND MIZUMOTO ET AL./11/. THERE ARE NO
NEW EXPERIMENTAL DATA AVAILABLE SINCE THE JENDL-2 EVALUATION.
TOTLA SPIN J AND ANGULAR MOMENTUM L OF SOME RESONANCES WERE
ESTIMATED WITH A RANDOM NUMBER METHOD AND A METHODOF BOLLINGER
AND THOMAS/12/, RESPECTIVELY.
THE CAPTURE CROSS SECTION OF JENDL-3.1 BETWEEN 1.3 AND 2.6
KEV IS TOO LOW COMPARED WITH INTERPOLATED VALUES FROM THE
LOWER AND HIGHER ENERGY REGIONS. TO COMPENSATE THE LOWER
CAPTURE CROSS SECTION, HYPOTHETICAL P-WAVE RESONANCES WERE
ADDED. THE OTHER DATA ARE THE SAME AS JENDL-3.1, EXCEPT FOR
NEUTRON WIDTH WHICH WAS MODIFIED SO AS TO REPRODUCE THE
CAPTURE AREA MEASURED BY MACKLIN/10/.
UNRESOLVED RESONANCE PARAMETERS (7.0095 - 100 KEV)
THE PARAMETERS WERE DETERMINED WITH THE CODE ASREP /13/ TO
REPRODUCE THE CAPTURE AND TOTAL CROSS SECTIONS, WHICH WERE
BASED ON EXPERIMENTAL DATA /14,15/ AND ADJUSTED FOR
CONSISTENCE BETWEEN THE DATA OF THE NATURAL ELEMENT AND ITS
ISOTOPES.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS):
2200 M/S RES. INTEG.
TOTAL 68.805 -
ELASTIC 5.180 -
CAPTURE 63.625 762.9
MF=3 NEUTRON CROSS SECTIONS
MT=1,102 TOTAL, CAPTURE
BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN. NO BACKGROUND
CROSS SECTIONS ARE ADOPTED. ABOVE 100 KEV, CROSS SECTIONS WERE
EVALUATED ON THE BASIS OF EXPERIMENTAL DATA AND THEORETICAL
CALCULATIONS. THE MAIN DATA WERE TAKEN FROM THE WORKS OF
POENITZ AND WHALEN /14/, FOSTER AND GLASGOW /16/ FOR TOTAL
CROSS SECTOIN AND MIZUMOTO ET AL. /15/, POENITZ/17/ FOR CAPTURE
CROSS SECTION. THE DATA WERE FITTED WITH SPLINE FUNCTION /18/,
AND WERE ADJUSTED FOR CONSISTENCE BETWEEN THE NATURAL ELEMENT
AND ITS ISOTOPES.
MT=2 ELASTIC
ELASTIC = TOTAL - NONELASTIC
MT=3 NONELASTIC
SUM OF MT=4,16,17,22,28,102,103,107
MT=4 TOTAL INELASTIC
SUM OF MT=51-80,91
MT=16,17,22,28,51-80,91,103,107 (N,2N),(N,3N),(N,NA),(N,NP),
INELASTIC,(N,P),(N,A)
THEY WERE MADE OF AG-107 AND AG-109 DATA. FOR THESE TWO
ISOTOPES, THE CROSS SECTIONS WERE CALCULATED WITH THE MULTISTEP
HAUSER-FESHBACH CODE TNG /19, 20/. AT FIRST, THE OPTICAL MODEL
AND LEVEL DENSITY PARAMETERS WERE TAKEN FROM THE WORKS OF SMITH
ET AL. /21/ AND IIJIMA ET AL. /22/, RESPECTIVELY AND THEN THEY
WERE ADJUSTED TO REPRODUCE AVAILABLE EXPERIMENTAL DATA.
FOR JENDL-3.2, INELASTIC SCATTERING CROSS SECTIONS AT
THRESHOLD ENERGIES OF OTHER LEVELS WERE INSERTED BY
INTERPOLATING THE CALUCULATED VALUES WITH AKIMA'S METHOD.
THE OPTICAL MODEL PARAMETERS ARE:
DEPTH (MEV) RADIUS(FM) DIFFUSENESS(FM)
----------------- ------------ ---------------
NEUTRON V = 48.25-0.3E R0 = 1.249 A0 = 0.603
WS = 8.501-0.15E RS = 1.270 AS = 0.575
VSO= 6.0 RSO= 1.249 ASO= 0.603
PROTON V = 66.061-0.550E R0 = 1.150 A0 = 0.650
WS = 12.50-0.10E RS = 1.250 AS = 0.470
RC = 1.150
ALPHA V = 193.0-0.15E R0 = 1.370 A0 = 0.560
WS = 21.00+0.25E RS = 1.370 AS = 0.560
RC = 1.370
THE LEVEL DENSITY PARAMETERS ARE:
ECUT(MEV) EJO(MEV) T(MEV) A(1/MEV) C(MEV) CSPIN EPAIR
RH-103 0.990 5.409 0.655 15.50 3.884 49.725 0.94
RH-104 0.230 4.351 0.650 15.43 17.72 49.820 0.00
RH-105 0.770 5.700 0.630 16.80 4.000 54.591 1.24
RH-106 0.150 3.869 0.575 17.50 17.18 57.230 0.00
PD-106 2.380 8.004 0.666 17.17 0.920 56.147 2.59
PD-107 0.700 7.693 0.769 14.98 6.956 49.293 1.35
PD-108 1.900 7.957 0.646 17.90 0.884 59.268 2.60
PD-109 0.360 7.380 0.687 17.50 9.479 58.301 1.35
AG-105 1.230 5.830 0.609 18.57 2.750 60.343 0.94
AG-106 0.400 3.549 0.563 17.16 12.92 56.110 0.00
AG-107 1.420 5.918 0.693 14.55 2.412 47.878 1.24
AG-108 0.270 3.014 0.576 15.04 6.004 49.799 0.00
AG-109 1.180 6.112 0.705 14.50 2.666 48.306 1.25
AG-110 0.320 3.150 0.454 17.01 2.513 57.015 0.00
THE LEVEL SCHEME IS GIVEN AS FOLLOWS:
AG-107:
NO. ENERGY(MEV) SPIN-PARITY
GR. 0.0 1/2 -
1 0.0930 7/2 +
2 0.1260 (9/2)+
3 0.3250 3/2 -
4 0.4230 5/2 -
5 0.7730 (11/2)+
6 0.7870 3/2 -
7 0.9220 5/2 +
8 0.9500 5/2 -
9 0.9730 (7/2)-
10 0.9910 (13/2)+
11 1.0610 (1/2 -)
12 1.1420 1/2 +
13 1.1470 7/2 -
14 1.2230 5/2 +
15 1.2590 (3/2)+
16 1.3260 (3/2)+
AG-109:
NO. ENERGY(MEV) SPIN-PARITY
GR. 0.0 1/2 -
1 0.0880 7/2 +
2 0.1330 9/2 +
3 0.3110 3/2 -
4 0.4150 5/2 -
5 0.7020 3/2 -
6 0.7070 3/2 +
7 0.7240 (3/2)+
8 0.7360 5/2 +
9 0.8630 5/2 -
10 0.8700 (5/2)+
11 0.9110 7/2 +
12 0.9120 7/2 -
13 1.0910 9/2 -
14 1.0990 (5/2 +)
MT=251
CALCULATED FROM MF=4,MT=2.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CALCULATED WITH THE CASTHY CODE /23/.
MT=51-80
CALCULATED WITH TNG.
MT=16,17,22,28,91
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,22,28,91
CALCULATED WITH TNG.
MF=12,14,15 GAMMA-PRODUCTION DATA
MT=4,16,17,22,28,102,103,107
CALCULATED WITH TNG.
REFERENCES
1) LIU, T. ET AL., JAERI-M 91-011 (1991).
2) NAKAJIMA, Y., TO BE PUBLISHED.
3) MOXON, M.C., RAE, E.R., "PROC. EANDC CONF. ON TIME-OF-FLIGHT
METHODS, SACLAY, 1961", 439.
4) GARG, J.B., ET AL., PHYS. REV., B137, 547(1965).
5) ASGHAR, M., ET AL., "PROC. INT. CONF. ON THE STUDY OF NUCLEAR
STRUCTURE WITH NEUTRONS, ANTWERP 1965", 65.
6) PATTENDEN N.J.,IBID.,532.
7) MURADJAN, G.V., ADAMCHUK, JU. V., JADERNO-FIZICHESKIE
ISSLEDOVANIJA, 6, 64 (1968).
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SCIENCE AND TECHNOLOGY", ANTWERP, P.226 (1982).
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576 (1971).
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18) NAKAGAWA, T., J. AT. ENE. SOC. JAPAN, 22, 559 (1980).
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22) IIJIMA, S., ET AL, J. NUCL. SCI. TECHNOL., 21, 10 (1984).
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