60-Nd-145
60-ND-145 JNDC EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.
DIST-SEP90 REV2-OCT93
----JENDL-3.2 MATERIAL 6034
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/
90-03 MODIFICATION FOR JENDL-3 WAS MADE/2/.
93-10 JENDL-3.2 WAS MADE BY JNDC FPND W.G.
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) RESOLVED RESONANCE PARAMETERS
***********************************************************
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 4 KEV
RESONANCE PARAMETERS WERE TAKEN FROM JENDL-2/3/ WITH
MODIFICATION OF TOTAL SPIN J.
FOR JENDL-2, RESONANCE ENERGIES WERE TAKEN FROM TELLIER
/4/, AND AFTER CALIBRATION, DATA OF ROHR ET AL./5/ AND
MUSGROVE ET AL./6/ WERE ADOPTED FOR THE LEVELS NOT MEASURED BY
TELLIER. NEUTRON WIDTHS WERE ADOPTED FROM TELLIER, AND RADIA-
TION WIDTHS WERE OBTAINED FROM THE CAPTURE AREAS MEASURED BY
ROHR ET AL. AND MUSGROVE ET AL. THE AVERAGE RADIATION WIDTH
OF 0.087 EV WAS ASSUMED FOR THE RESONANCES WHOSE CAPTURE AREA
WAS NOT MEASURED, AND TO ESTIMATE NEUTRON WIDTHS FROM THE
CAPTURE AREAS FOR THE RESONANCES NOT MEASURED BY TELLIER. A
NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL
CAPTURE AND TOTAL CROSS SECTIONS GIVEN BY MUGHABGHAB ET AL./7/
FOR JENDL-3, TOTAL SPIN J OF SOME RESONANCES WAS TENTATIVE-
LY ESTIMATED WITH A RANDOM NUMBER METHOD.
FOR JENDL-3.2, THE CAPTURE DATA MEASURED AT ORELA OF ORNL
WERE RENORMALIZED (FACTOR = 0.9507)/8/. THE NEUTRON WIDTH
AND/OR THE RADIATION WIDTH WAS REVISED TO REPRODUCE THE
RENORMALIZED CAPTURE AREA FOR EACH RESONANCE ABOVE 2.592 KEV.
UNRESOLVED RESONANCE REGION : 4 KEV - 100 KEV
UNRESOLVED RESONANCE PARAMETERS WERE ADOPTED FROM JENDL-2.
THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED
WITH OPTICAL MODEL CODE CASTHY/9/. 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.
TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:
S0 = 2.927E-4, S1 = 0.685E-4, S2 = 3.510E-4, SG = 54.7E-4,
GG = 0.0975EV, R = 7.683 FM.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)
2200 M/S RES. INTEG.
TOTAL 64.065 -
ELASTIC 20.222 -
CAPTURE 43.843 204
(N,ALPHA) 8.855E-05 2.03E-3
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/10/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP
EVAPORATION MODEL. THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE
DETERMINED BY IIJIMA AND KAWAI/11/ TO REPRODUCE A SYSTEMATIC
TREND OF THE TOTAL CROSS SECTION.
THE OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:
PROTON = PEREY/12/
ALPHA = HUIZENGA AND IGO/13/
DEUTERON = LOHR AND HAEBERLI/14/
HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/15/
PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT
AND CAMERON/16/ WERE EVALUATED BY IIJIMA ET AL./17/ 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
/18/.
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./19/.
NO. ENERGY(MEV) SPIN-PARITY
GR. 0.0 7/2 -
1 0.0671 3/2 -
2 0.0722 5/2 -
3 0.5066 3/2 -
4 0.6570 11/2 -
5 0.7490 9/2 -
6 0.7804 3/2 -
7 0.8407 3/2 -
8 0.9202 1/2 -
9 0.9371 5/2 -
10 1.0112 11/2 -
11 1.0514 7/2 -
12 1.0852 3/2 +
13 1.1503 9/2 -
14 1.1610 5/2 -
15 1.1620 9/2 -
16 1.2500 5/2 -
LEVELS ABOVE 1.3 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/20/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.
THE GAMMA-RAY STRENGTH FUNCTION (5.58E-03) WAS ADJUSTED TO
REPRODUCE THE CAPTURE CROSS SECTION OF 510 MILLI-BARNS AT 30
KEV MEASURED BY NAKAJIMA ET AL./21/
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 (= 168.3) WAS ESTIMATED BY THE
FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/22/ 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) 7.50 MB (RECOMMENDED BY FORREST/23/)
(N,ALPHA) 2.47 MB (SYSTEMATICS OF FORREST/23/)
THE (N,ALPHA) CROSS SECTION BELOW 4 KEV WAS CALCULATED FROM
RESONANCE PARAMETERS, BY ASSUMING A MEAN ALPHA WIDTH OF
1.50E-7 EV SO AS TO REPRODUCE THE THERMAL CROSS SECTION/7/.
THE CROSS SECTION WAS AVERAGED IN SUITABLE ENERGY INTERVALS.
ABOVE 4 KEV, THE CROSS SECTION WAS CONNECTED SMOOTHLY TO THE
PEGASUS CALCULATION.
MT = 251 MU-BAR
CALCULATED WITH CASTHY/9/.
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 = 47.94 R0 = 6.718 A0 = 0.6
WS = 9.13 RS = 7.564 AS = 0.45
VSO= 7.0 RSO= 6.771 ASO= 0.6
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
---------------------------------------------------------------
58-CE-141 1.714E+01 5.150E-01 7.134E-01 3.957E+00 1.170E+00
58-CE-142 1.600E+01 6.000E-01 4.210E-01 5.674E+00 1.930E+00
58-CE-143 1.900E+01 5.500E-01 2.613E+00 5.094E+00 1.170E+00
58-CE-144 1.700E+01 6.000E-01 5.074E-01 6.214E+00 2.090E+00
59-PR-142 1.595E+01 6.150E-01 1.201E+01 3.974E+00 0.0
59-PR-143 1.500E+01 6.280E-01 2.607E+00 4.558E+00 7.600E-01
59-PR-144 1.600E+01 6.000E-01 1.045E+01 3.744E+00 0.0
59-PR-145 * 2.088E+01 5.411E-01 7.911E+00 5.258E+00 9.200E-01
60-ND-143 1.826E+01 4.710E-01 5.220E-01 3.613E+00 1.180E+00
60-ND-144 1.771E+01 5.640E-01 4.792E-01 5.691E+00 1.940E+00
60-ND-145 2.054E+01 5.120E-01 2.465E+00 4.869E+00 1.180E+00
60-ND-146 2.019E+01 5.660E-01 1.121E+00 6.714E+00 2.100E+00
---------------------------------------------------------------
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 6.875 FOR ND-145 AND 6.125 FOR ND-146.
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