63-Eu-154
63-EU-154 JNDC EVAL-DEC90 JNDC FP NUCLEAR DATA W.G.
DIST-MAR02 REV3-FEB02 20020222
----JENDL-3.3 MATERIAL 6334
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
JENDL-3.2 data were automatically transformed to JENDL-3.3.
Interpolation of spectra: 22 (unit base interpolation)
(3,251) deleted, T-matrix of (4,2) deleted, and others.
===========================================================
HISTORY
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/
90-03 MODIFICATION FOR JENDL-3 WAS MADE/2/.
90-12 STATISTICAL MODEL CALUCULATION WAS MADE BY RENORMALIZING
THE CAPTURE CROSS SECTION.
93-11 JENDL-3.2 WAS MADE BY JNDC FPND W.G.
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) RESOLVED RESONANCE PARAMETERS. NEGATIVE
RESONANCE PARAMETERS WERE MODIFIED.
***********************************************************
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) : BELOW 0.0262 KEV
RESONANCE PARAMETERS IN JENDL-2 WERE REPLACED WITH THE RECOM-
MENDATION BY MUGHABGHAB/3/. TOTAL SPIN J WAS TENTATIVELY
ESTIMATED WITH A RANDOM NUMBER METHOD. PARAMETERS OF THE
NEGATIVE LEVEL WERE ADJUSTED TO THE THERMAL CAPTURE CROSS
SECTION AND RESONANCE INTEGRAL MEASURED BY SEKINE ET AL./4/
UNRESOLVED RESONANCE REGION : 0.0262 KEV - 100 KEV
THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED
WITH OPTICAL MODEL CODE CASTHY/5/.
THE OBSERVED LEVEL SPACING WAS DETERMINED TO REPRODUCE THE
CAPTURE CROSS SECTION CALCULATED WITH CASTHY. THE
EFFECTIVE SCATTERING RADIUS WAS OBTAINED FROM FITTING TO THE
CALCULATED TOTAL CROSS SECTION AT 100 KEV.
THE RADIATION WIDTH WAS BASED ON THE COMPILATION OF
MUGHABGHAB /3/.
TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:
S0 = 2.200E-4, S1 = 0.940E-4, S2 = 2.300E-4, SG = 2740.E-4,
GG = 0.126 EV, R = 7.006 FM.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)
2200 M/S RES. INTEG.
TOTAL 1848.2 -
ELASTIC 6.581 -
CAPTURE 1841.6 1180
MF = 3 NEUTRON CROSS SECTIONS
BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.
ABOVE 100 KEV, THE SPHERICAL OPTICAL AND STATISTICAL MODEL
CALCULATION WAS PERFORMED WITH CASTHY, BY TAKING ACCOUNT OF
COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED
WITH PEGASUS/6/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP
EVAPORATION MODEL. THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE
DETERMINED SO AS TO REPRODUCE THE EU-NATURAL TOTAL CROSS SECTION
MEASURED BY FOSTER AND GLASGOW/7/. THE OMP'S FOR CHARGED
PARTICLES ARE AS FOLLOWS:
PROTON = PEREY/8/
ALPHA = HUIZENGA AND IGO/9/
DEUTERON = LOHR AND HAEBERLI/10/
HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/11/
PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT
AND CAMERON/12/ WERE EVALUATED BY IIJIMA ET AL./13/ MORE
EXTENSIVE DETERMINATION AND MODIFICATION WERE MADE IN THE
PRESENT WORK. TABLE 2 SHOWS THE LEVEL DENSITY PARAMETERS USED
IN THE PRESENT CALCULATION. ENERGY DEPENDENCE OF SPIN CUT-OFF
PARAMETER IN THE ENERGY RANGE BELOW E-JOINT IS DUE TO GRUPPELAAR
/14/.
MT = 1 TOTAL
SPHERICAL OPTICAL MODEL CALCULATION WAS ADOPTED.
MT = 2 ELASTIC SCATTERING
CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).
MT = 4, 51 - 91 INELASTIC SCATTERING
SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WAS
ADOPTED. THE LEVEL SCHEME WAS TAKEN FROM REF./15/.
NO. ENERGY(MEV) SPIN-PARITY
GR. 0.0 3 -
1 0.0682 4 +
2 0.0957 4 +
3 0.0971 5 +
4 0.1000 5 -
5 0.1008 4 +
6 0.1367 5 +
7 0.1800 8 -
LEVELS ABOVE 0.2 MEV WERE ASSUMED TO BE OVERLAPPING.
MT = 102 CAPTURE
SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WITH
CASTHY WAS ADOPTED. DIRECT AND SEMI-DIRECT CAPTURE CROSS
SECTIONS WERE ESTIMATED ACCORDING TO THE PROCEDURE OF BENZI
AND REFFO/16/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.
THE GAMMA-RAY STRENGTH FUNCTION (2840.0E-4) WAS ADJUSTED TO
REPRODUCE THE CAPTURE CROSS SECTION OF 2610 MILLI-BARNS AT 50
KEV WHICH WAS 20 % LARGER THAN JENDL-2 CALCULATION/17/.
NOTE : RESULTS OF PREVIOUS INTEGRAL TEST OF JENDL-2/1,17/ WERE
REFLECTED IN THE PRESENT EVALUATION.
MT = 16 (N,2N) CROSS SECTION
MT = 17 (N,3N) CROSS SECTION
MT = 22 (N,N'A) CROSS SECTION
MT = 28 (N,N'P) CROSS SECTION
MT = 32 (N,N'D) CROSS SECTION
MT = 33 (N,N'T) CROSS SECTION
MT =103 (N,P) CROSS SECTION
MT =104 (N,D) CROSS SECTION
MT =105 (N,T) CROSS SECTION
MT =107 (N,ALPHA) CROSS SECTION
THESE REACTION CROSS SECTIONS WERE CALCULATED WITH THE
PREEQUILIBRIUM AND MULTI-STEP EVAPORATION MODEL CODE PEGASUS.
THE KALBACH'S CONSTANT K (= 183.4) WAS ESTIMATED BY THE
FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/18/ AND LEVEL
DENSITY PARAMETERS.
FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE
NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:
(N,P) 4.32 MB (SYSTEMATICS OF FORREST/19/)
(N,ALPHA) 1.68 MB (SYSTEMATICS OF FORREST)
MT = 251 MU-BAR
CALCULATED WITH CASTHY.
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. FOR OTHER REACTIONS, ISOTROPIC DISTRI-
BUTIONS IN THE LABORATORY SYSTEM WERE ASSUMED.
MF = 5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE CALCULATED WITH
PEGASUS FOR INELASTIC SCATTERING TO OVERLAPPING LEVELS AND FOR
OTHER NEUTRON EMITTING REACTIONS.
TABLE 1 NEUTRON OPTICAL POTENTIAL PARAMETERS
DEPTH (MEV) RADIUS(FM) DIFFUSENESS(FM)
---------------------- ------------ ---------------
V = 44.77-0.0164E R0 = 6.818 A0 = 0.475
WS = 6.878-0.1408E RS = 7.719 AS = 0.45
VSO= 7.0 RSO= 6.818 ASO= 0.48
THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.
TABLE 2 LEVEL DENSITY PARAMETERS
NUCLIDE SYST A(1/MEV) T(MEV) C(1/MEV) EX(MEV) PAIRING
---------------------------------------------------------------
61-PM-150 2.270E+01 3.800E-01 7.943E+00 1.973E+00 0.0
61-PM-151 2.882E+01 4.260E-01 8.842E+00 4.956E+00 1.110E+00
61-PM-152 * 2.440E+01 5.242E-01 1.481E+02 5.009E+00 0.0
61-PM-153 2.285E+01 4.950E-01 7.324E+00 4.895E+00 9.200E-01
62-SM-151 2.687E+01 5.000E-01 2.313E+01 6.327E+00 1.220E+00
62-SM-152 2.375E+01 5.470E-01 2.365E+00 7.669E+00 2.330E+00
62-SM-153 2.572E+01 5.160E-01 2.101E+01 6.405E+00 1.220E+00
62-SM-154 2.190E+01 5.600E-01 1.960E+00 7.188E+00 2.140E+00
63-EU-152 2.484E+01 4.850E-01 8.700E+01 4.264E+00 0.0
63-EU-153 2.195E+01 5.750E-01 1.698E+01 6.504E+00 1.110E+00
63-EU-154 2.267E+01 4.320E-01 1.644E+01 2.784E+00 0.0
63-EU-155 2.083E+01 5.200E-01 5.190E+00 4.837E+00 9.200E-01
---------------------------------------------------------------
SYST: * = LDP'S WERE DETERMINED FROM SYSTEMATICS.
SPIN CUTOFF PARAMETERS WERE CALCULATED AS 0.146*SQRT(A)*A**(2/3).
IN THE CASTHY CALCULATION, SPIN CUTOFF FACTORS AT 0 MEV WERE
ASSUMED TO BE 15.98 FOR EU-154 AND 8.187 FOR EU-155.
REFERENCES
1) AOKI, T. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC
AND APPLIED SCIENCE, SANTA FE., VOL. 2, P.1627 (1985).
2) KAWAI, M. ET AL.: J. NUCL. SCI. TECHNOL., 29, 195 (1992).
3) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS, VOL. I, PART B",
ACADEMIC PRESS (1984).
4) SEKINE, T. ET AL.: APPL. RADIAT. ISOT., 38, 513 (1987).
5) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).
6) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).
7) FOSTER, D.G. JR. AND GLASGOW, D.W.: PHYS. REV., C3, 576
(1971).
8) PEREY, F.G: PHYS. REV. 131, 745 (1963).
9) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).
10) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).
11) BECCHETTI, F.D., JR. AND GREENLEES, G.W.: POLARIZATION
PHENOMENA IN NUCLEAR REACTIONS ((EDS) H.H. BARSHALL AND
W. HAEBERLI), P. 682, THE UNIVERSITY OF WISCONSIN PRESS.
(1971).
12) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446
(1965).
13) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).
14) GRUPPELAAR, H.: ECN-13 (1977).
15) MATSUMOTO, J.: PRIVATE COMMUNICATION (1981).
16) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).
17) WATANABE, T. ET AL.: JAERI-M 88-065, P. 148 (1988).
18) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR
REACTIONS", NORTH HOLLAND (1968).
19) FORREST, R.A.: AERE-R 12419 (1986).