63-Eu- 0
63-EU- 0 JAERI,JNDC EVAL-MAR89 T.ASAMI, JNDC FP ND W.G.
DIST-OCT89 REV2-NOV93
----JENDL-3.2 MATERIAL 6300
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
89-03 EVALUATION FOR EACH ISOTOPE WAS MADE BY T.ASAMI(JAERI) AND
JNDC FP NUCLEAR DATA W.G. DATA FOR NATURAL EU WERE
CONSTRUCTED FROM THE ISOTOPE DATA BY T.ASAMI AND
T.NAKAGAWA(JAERI).
90-06 (MF3,MT251) MODIFIED.
93-11 JENDL-3.2
GAMMA-RAY PRODUCTION DATA RE-EVALUATED BY T.ASAMI(DATA ENG.)
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) SMALL MODIFICATION OF EU-153 PARAMETERS.
(3,102) Q-VALUES WERE CAHNGED.
(12,102) BELOW 21.64 KEV
(15,102) BELOW 21.64 KEV
***********************************************************
MF = 1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY
MF = 2 RESONANCE PARAMETERS
MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS
RESOLVED RESONANCE REGION (MLBW FORMULA)
EVALUATION FOR EACH ISOTOPE WAS MADE BY KIKUCHI /1/.
1) EU-151: BELOW 98.2 EV
PARAMETERS WERE MAINLY BASED ON THE DATA OF RAHN ET AL.
/2/, AND FOR THE LOWEST 2 LEVELS, THE DATA OF TASSAN ET
AL./3/. THE CAPTURE WIDTH OF 0.093 EV /2/ WAS ASSUMED FOR
THE LEVELS WHOSE RADIATIVE CAPTURE WIDTH WAS NOT MEASURED.
A NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE
CAPTURE CROSS SECTION OF 9200 BARNS AT 0.0253 EV/4/.
2) EU-153: BELOW 97.2 EV
NEUTRON WIDTHS WERE OBTAINED FROM THE DATA OF RAHN ET AL.
/2/ AND ANUFRIEV ET AL./5/. RADIATIVE CAPTURE WIDTHS WERE
ADOPTED FROM THE DATA OF RAHN ET AL. THE PARAMETERS OF
1.73-, 2.46-, 3.29- AND 3.94-EV LEVELS WERE TAKEN FROM
MAGHABGHAB /6/ SO AS TO REPRODUCE THE CAPTURE RESONANCE
INTEGRAL OF 1420 BARNS/6/. A NEGATIVE RESONANCE WAS ADDED
SO AS TO REPRODUCE THE CAPTURE CROSS SECTION OF 390 BARNS
AND THE ELASTIC SCATTERING OF 8.0 +- 0.2 BARNS AT 0.0253
EV/4/.
UNRESOLVED RESONANCE REGION : UP TO 100 KEV
THE PARAMETERS WERE ADJUSTED TO REPRODUCE THE CAPTURE CROSS
SECTIONS. THE EFFECTIVE SCATTERING RADIUS WAS OBTAINED FROM
FITTING TO THE CALCULATED TOTAL CROSS SECTION AT 100 KEV.
TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:
1) EU-151
S0 = 3.699E-4, S1 = 0.100E-4, S2 = 3.000E-4, GG = 0.091 EV
DO = 0.408 EV, R = 6.870 FM.
2) EU-153
S0 = 2.602E-4, S1 = 1.394E-4, S2 = 2.946E-4, GG = 0.094 EV
DO = 1.489 EV, R = 6.421 FM.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)
2200 M/S RES. INTEG.
TOTAL 4566.6 -
ELASTIC 6.925 -
CAPTURE 4559.7 2202
(N,ALPHA) 4.637E-06
MF = 3 NEUTRON CROSS SECTIONS
BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.
MT = 1 TOTAL
BELOW 10 MEV, CALCULATED WITH THE CASTHY CODE/7/. THE OPTICAL
POTENTIAL PARAMETERS LISTED IN TABLE 1 USED. ABOVE 10 MEV,
CROSS SECTION WAS DETERMINED FROM THE DATA OF FOSTER AND
GLASGOW/8/ FOR NATURAL EU.
MT = 2 ELASTIC SCATTERING
CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).
MT = 4, 51-71, 91 INELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE/7/. THE LEVEL SCHEME USED IN
THE CALCULATIONS WAS TAKEN FROM REF./9/
EU-151 EU-153
NO MT ENERGY(MEV) J-PARITY NO. MT ENERGY(MEV) J-PARITY
G.S 0.0 5/2+ G.S 0.0 5/2+
1 51 0.02150 7/2+ 1 52 0.0834 7/2+
2 58 0.19620 11/2- 2 53 0.0974 5/2-
3 59 0.19650 3/2+ 3 54 0.1032 3/2+
4 61 0.2432 7/2- 4 55 0.1516 7/2-
5 62 0.2604 5/2+ 5 56 0.1729 5/2+
6 64 0.3070 7/2+ 6 57 0.1931 9/2+
7 65 0.3075 5/2+ 7 60 0.2353 9/2-
8 68 0.3498 9/2- 8 63 0.2697 7/2+
9 69 0.3536 7/2- 9 66 0.3219 11/2-
10 71 0.4160 7/2+ 10 67 0.3251 11/2+
11 70 0.3964 9/2+
CONT 91 0.420 CONT 91 0.400
Q-VALUES OF EXCITED LEVELS WERE SHIFTED A LITTLE SO
AS TO BE CONSISTENT WITH THRESHOLD ENERGIES.
MT = 102 CAPTURE
CALCULATED FROM EU-151 AND -153 CAPTURE CROSS SECTIONS.
THE EU-151 CAPTURE CROSS SECTION BELOW 2 MEV WAS DETERMINED BY
EYE-GUIDING THE DATA MEASURED BY MACKLIN AND YOUNG/10/, AND
ABOVE 2 MEV, JENDL-2 DATA CALCULATED WITH CASTHY WAS
NORMALIZED TO MACKLIN AND YOUNG AT 2 MEV. FOR EU-153,
EVALUATION FOR JENDL-2 WAS ADOPTED. DIRECT AND SEMI-DIRECT
CAPTURE CROSS SECTIONS WERE ADDED, WHICH WERE ESTIMATED
ACCORDING TO THE PROCEDURE OF BENZI AND REFFO/11/ AND
NORMALIZED TO 1 MILLI-BARN AT 14 MEV.
Q-VALUE WAS DETERMINED BY WEIGHTED AVERAGE.
MT=16, 17, 22, 28, 103, 107 (N,2N), (N,3N), (N,NA), (N,NP),
(N,P) AND (N,A) CROSS SECTIONS
CALCULATED WITH THE GNASH CODE/12/ USING THE OPTICAL MODEL
PARAMETERS IN TABLE 2, WHICH WERE DETERMINED SO AS TO
REPRODUCE WELL THE TOTAL CROSS SECTION MEASURED BY FOSTER AND
GLASGOW/8/ FOR NATURAL EU. THE LEVEL SCHEME DATA WERE TAKEN
FROM REF./9/. THE CALCULATED (N,2N) AND (N,3N) CROSS SECTIONS
WERE MODIFIED ON THE BASIS OF THE EXPERIMENTAL DATA OF FREHAUT
ET AL./13/ AND BAYHURT/14/, RESPECTIVELY.
THE (N,ALPHA) CROSS SECTION IN THE RESONANCE REGION WAS
CALCULATED FROM RESONANCE PARAMETERS, BY ASSUMING A MEAN ALPHA
WIDTH OF 9.0E-11 EV FOR EU-151 AND 2.0E-10 EV FOR EU-153 SO AS
TO REPRODUCE THE THERMAL CROSS SECTION/6/. THE CROSS SECTION
WAS AVERAGED IN SUITABLE ENERGY INTERVALS. ABOVE THE RESOLVED
RESONANCE REGION, THE CROSS SECTION WAS CONNECTED SMOOTHLY TO
THE GNASH CALCULATION.
MT = 251 MU-BAR
CALCULATED WITH CASTHY/7/.
MF = 4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
LEGENDRE POLYNOMIAL COEFFICIENTS FOR ANGULAR DISTRIBUTIONS ARE
GIVEN IN THE CENTER-OF-MASS SYSTEM FOR MT=2 AND DISCRETE INELAS-
TIC LEVELS, AND IN THE LABORATORY SYSTEM FOR MT=91. THEY WERE
CALCULATED WITH CASTHY/7/. FOR OTHER REACTIONS, THE ISOTROPIC
DISTRIBUTIONS IN THE LABORATORY SYSTEM WERE ASSUMED.
MF = 5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE CALCULATED WITH
GNASH/12/.
MF = 12 PHOTON PRODUCTION MULTIPLICITIES
MT=102 (BELOW 21.6437 KEV)
CALCULUATED FROM ENERGY BALANCE.
MT=107 (BELOW 21.6437 KEV)
CALCULUATED WITH GNASH CODE/12/.
MF = 13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 21.6437 KEV)
CALCULUATED WITH GNASH CODE/12/.
MF = 14 PHOTON ANGULAR DISTRIBUTIONS
MT=3, 102
ASSUMED TO BE ISOTROPIC.
MF = 15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3, 102, 107
CALCULATED WITH GNASH CODE/12/. SPECTRA OF MT=102 AT 1.0E-5
EV AND 0.0253 EV WERE CALCULATED WITH CASTHY/7/.
TABLE 1 NEUTRON OPTICAL POTENTIAL PARAMETERS (FOR CASTHY)
V = 43.71 - 0.0566*EN, VSO = 7.9 (MEV)
WS = 7.696, WV = 0.0 (MEV)
R = 1.270, RS = 1.440, RSO = 1.280 (FM)
A = 0.60, B = 0.45, ASO = 0.60 (FM)
TABLE 2 NEUTRON OPTICAL POTENTIAL PARAMETERS (FOR GNASH)
V = 43.71 - 0.05655*EN, VSO = 0.0 (MEV)
WS = 7.696, WV = 0.0 (MEV)
R = 1.272, RS = 1.440, RSO = 1.270 (FM)
A = 0.48, B = 0.45, ASO = 0.48 (FM)
REFERENCES
1) KIKUCHI, Y. ET AL.: JAERI-M 86-030 (1986).
2) RAHN, F., ET AL.: PHYS. REV., C6, 251 (1972).
3) TASSAN, S., ET AL.: NUCL. SCI., ENG., 10, 169 (1961).
4) MUGHABGHAB, S.F., GARBER, D.I.: "NEUTRON CROSS SECTIONS,
VOL.1, RESONANCE PARAMETERS", BNL 325, 3RD ED., VOL. 1,
(1973).
5) ANUFRIEV, V.A., ET AL.: SOV. AT. ENERGY, 46, 182 (1979).
6) MUGHABGHAB, S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. I,
PART A", ACADEMIC PRESS (1981).
7) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).
8) FOSTER JR.D.G. AND GLASGOW D.W.: PHYS. REV., C3, 576 (1971).
9) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE (JUNE 1987).
10) MACKLIN, R.L. AND YOUNG, P.G.: NUCL. SCI. ENG., 95, 189(1987).
11) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).
12) YOUNG, P.G. AND ARTHUR, E.D.: LA-6947 (1977).
13) FREHAUT, J. ET AL.: DATA (1980) IN THE EXFOR FILE.
14) BAYHURST, B.P. ET AL.: PHYS. REV., C12, 451 (1975).