38-Sr- 88
38-SR- 88 JNDC EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.
DIST-MAR02 REV3-FEB02 20020222
----JENDL-3.3 MATERIAL 3837
-----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/.
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 300 KEV
RESOLVED RESONANCE PARAMETERS FOR JENDL-3 WERE TAKEN FROM
JENDL-2 WHICH WAS EVALUATED ON THE BASIS OF THE MEASUREMENTS
BILPUCH ET AL./3/, CAMARDA ET AL./4/, MALAN ET AL./5/ AND
BOLDEMAN ET AL./6/.
FOR JENDL-3, RADIATION WIDTHS OF THE 1ST AND 5TH RESONANCE
LEVELS (L=0) AT 2.78 AND 13.8 KEV WERE MODIFIED TO 190 AND 106
MEV, RESPECTIVELY, SO AS TO REPRODUCE THE THERMAL CAPTURE
CROSS SECTION OF 5.8+-0.4 MB GIVEN BY ROY ET AL./7/ SCATTERING
RADIUS OF 7.1 FM WAS TAKEN FROM MUGHABGHAB ET AL./8/
FOR JENDL-3.2, THESE RESONANCE PARAMETERS WERE MODIFIED SO
AS TO REPRODUCE THE CAPTURE AREA DATA MEASURED AT ORNL, BY
TAKING ACCOUNT OF THE CORRECTION FACTOR (1.0737) ANNOUNCED BY
ALLEN ET AL./9/
NO UNRESOLVED RESONANCE REGION
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)
2200 M/S RES. INTEG.
TOTAL 5.436 -
ELASTIC 5.431 -
CAPTURE 0.0058 0.0633
MF = 3 NEUTRON CROSS SECTIONS
BELOW 300 KEV, RESONANCE PARAMETERS WERE GIVEN.
ABOVE 300 KEV, THE SPHERICAL OPTICAL AND STATISTICAL MODEL
CALCULATION WAS PERFORMED WITH CASTHY/10/, BY TAKING ACCOUNT OF
COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED
WITH PEGASUS/11/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP
EVAPORATION MODEL. THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE
DETERMINED BY IIJIMA AND KAWAI/12/ TO REPRODUCE A SYSTEMATIC
TREND OF THE TOTAL CROSS SECTION. THE OMP'S FOR CHARGED
PARTICLES ARE AS FOLLOWS:
PROTON = PEREY/13/
ALPHA = HUIZENGA AND IGO/14/
DEUTERON = LOHR AND HAEBERLI/15/
HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/16/
PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT
AND CAMERON/17/ WERE EVALUATED BY IIJIMA ET AL./18/ 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
/19/.
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./20/.
NO. ENERGY(MEV) SPIN-PARITY
GR. 0.0 0 +
1 1.8360 2 +
2 2.7341 3 -
3 3.1510 0 +
4 3.2185 2 +
5 3.4865 1 +
6 3.5239 2 +
7 3.5846 5 -
8 3.6344 3 +
9 3.9526 4 +
10 3.9900 3 -
11 4.0355 2 +
12 4.1701 4 -
13 4.2240 3 +
14 4.2320 4 +
15 4.2693 3 -
16 4.2980 4 +
17 4.4137 3 +
18 4.4520 4 +
19 4.4840 0 +
20 4.5139 2 -
21 4.6190 2 +
LEVELS ABOVE 4.636 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/21/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.
THE GAMMA-RAY STRENGTH FUNCTION (0.0375E-04) WAS ADJUSTED TO
REPRODUCE THE CAPTURE CROSS SECTION OF 2.8 MILLI-BARNS AT 100
KEV MEASURED BY MUSGROVE ET AL./22,9/
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 =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 (= 380.2) WAS ESTIMATED BY THE
FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/23/ 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) 15.00 MB (RECOMMENDED BY FORREST/24/)
(N,ALPHA) 4.45 MB (SYSTEMATICS OF FORREST/24/)
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 = 46.0-0.25E R0 = 5.893 A0 = 0.62
WS = 7.0 RS = 6.393 AS = 0.35
VSO= 7.0 RSO= 5.893 ASO= 0.62
THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.
TABLE 2 LEVEL DENSITY PARAMETERS
NUCLIDE A(1/MEV) T(MEV) C(1/MEV) EX(MEV) PAIRING
---------------------------------------------------------------
36-KR- 84 9.970E+00 9.600E-01 4.942E-01 8.590E+00 2.630E+00
36-KR- 85 1.024E+01 8.900E-01 1.570E+00 6.261E+00 1.170E+00
36-KR- 86 9.052E+00 8.686E-01 2.185E-01 5.874E+00 2.100E+00
36-KR- 87 9.400E+00 8.860E-01 8.826E-01 5.481E+00 1.170E+00
37-RB- 85 1.190E+01 8.690E-01 2.827E+00 7.561E+00 1.460E+00
37-RB- 86 1.002E+01 8.500E-01 3.954E+00 4.312E+00 0.0
37-RB- 87 8.806E+00 9.410E-01 1.125E+00 5.465E+00 9.300E-01
37-RB- 88 9.801E+00 8.185E-01 2.880E+00 3.704E+00 0.0
38-SR- 86 1.120E+01 8.900E-01 5.328E-01 8.599E+00 2.700E+00
38-SR- 87 1.030E+01 8.610E-01 1.186E+00 5.938E+00 1.240E+00
38-SR- 88 9.160E+00 7.510E-01 8.288E-02 4.550E+00 2.170E+00
38-SR- 89 9.380E+00 8.200E-01 5.043E-01 4.642E+00 1.240E+00
---------------------------------------------------------------
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 5.839 FOR SR- 88 AND 5.818 FOR SR- 89.
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) BILPUCH, E.G., ET AL.: ANN. PHYS., 14, 387 (1961).
4) CAMARDA, H., ET AL.: NCSAC-31, 40 (1970).
5) MALAN, J.G., ET AL.: ANN. PHYS., 89, 284 (1975).
6) BOLDEMAN, J.W., ET AL.: NUCL. PHYS., A269, 397 (1976).
7) ROY, ET AL.: CAN. J. CHEM., 36, 731 (1958), THE DATA WAS
TAKEN FROM WALKER, W.H.: AECL-3037, PART I (1969).
8) MUGHABGHAB, S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. I,
PART A", ACADEMIC PRESS (1981).
9) ALLEN, B.J., ET AL.: NUCL. SCI. ENG., 82, 230 (1982).
10) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).
11) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).
12) IIJIMA, S. AND KAWAI, M.: J. NUCL. SCI. TECHNOL., 20, 77
(1983).
13) PEREY, F.G: PHYS. REV. 131, 745 (1963).
14) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).
15) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).
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PHENOMENA IN NUCLEAR REACTIONS ((EDS) H.H. BARSHALL AND
W. HAEBERLI), P. 682, THE UNIVERSITY OF WISCONSIN PRESS.
(1971).
17) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446
(1965).
18) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).
19) GRUPPELAAR, H.: ECN-13 (1977).
20) MATSUMOTO, J.: PRIVATE COMMUNICATION (1981).
21) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).
22) MUSGROVE, A.R. DE L., ET AL.: PROC. INT. CONF. ON NEUTRON
PHYSICS AND NUCL. DATA FOR REACTORS, HARWELL 1978, 449.
23) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR
REACTIONS", NORTH HOLLAND (1968).
24) FORREST, R.A.: AERE-R 12419 (1986).