16-S - 32 FUJI E.C. EVAL-MAY87 H.NAKAMURA
DIST-MAY10 20090828
----JENDL-4.0 MATERIAL 1625
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
The data were taken from JENDL-3.3.
===========================================================
HISTORY
87-03 Newly evaluated by H.Nakamura (fuji electric co.ltd.)
88-08 The following quantities were modified by H.Nakamura:
(n,p) cross section
inelastic scattering cross sections and angular
distributions of the first, third and continuum levels
94-02 JENDL-3.2
Coupled-channel calculation was performed by K. Shibata
(jaeri) using the omp set determined by T. Watanabe (khi).
the total and inelastic scattering cross sections were
replaced by the c.c. calculations.
Data were compiled by K. Shibata.
***** modified parts for JENDL-3.2 ****************************
(3,1),(3,4),(3,51-56,91),(3,251),(4,2),(4,51-56)
coupled-channel calculations.
(3,2) total - nonelastic
****************************************************************
01-04 JENDL-3.3
Gamma-ray production data were evaluated and compiled
by K. Shibata
***** modified parts for JENDL-3.3 ****************************
(1,451) Updated
(3,251) Deleted.
(4,2) Transformation matrix deleted.
(5,16-91) INT=22.
(12,16-107) Added.
(14,16-107) Added.
(15,16-107) Added.
****************************************************************
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 mt=151 Resonance parameters:
Resolved resonances for MLBW formula: 1.0e-5 eV - 1566 keV
parameters are taken from BNL 325 4th edition/1/, and
some parameters are assumed to fit the measured data.
cross sections calculated with these parameters are to
be corrected by adding mf=3, mt=1, 2 and 102 data.
calculated 2200-m/s cross sections and resonance integrals
2200-m/sec res. integ. ref.
elastic 0.963 b - -
capture 0.528 b 0.250 b /1/
total 1.499 b - -
mf=3 Neutron cross sections
Below 1566keV
background data for
mt=107 0.007 b, based on 2200-m/s data of ref./1/.
Above 1566keV
mt=1, 2, 4, 51-56, 91, 102 Total, elastic, inelastic and
capture calculated with casthy code /2/, considering the
competition with the threshold reaction channels.
Optical potential parameters of C.Y.Fu/3/ are adjusted
to reproduce the following experimental data:
mt=1 total -
mt=2 elastic G.A.Petitt et al./4/, A.Virdis/5/.
mt=4 inelastic -
The spherical optical potential parameters:
V=38.0 Vso=5.37 (MeV)
Ws=9.13 Wv =0.0 (MeV)
r =rso=1.26 rs=1.39 (fm)
a=aso =0.76 b =0.40(fm)
mt=102 Capture data are normalized to the experimental
data of A.Lindholm et al. at 3 - 6 MeV/6/.
The discrete level scheme taken from ref./7/:
no. energy(MeV) spin-parity
(g.s.) 0.0 0+
1 2.230 2+
2 3.779 0+
3 4.282 2+
4 4.459 4+
5 4.695 1+
6 5.006 3-
Continuum levels assumed above 5.4 MeV. The level
density parameters of Asano et al./8/are used.
***** JENDL-3.2 ****************************************
mt=1,4,51-56,91,251
Coupled-channel optical and statistical model calculation
was performed by using the omp set given as follows:
V = 58.83 - 0.5635En (MeV)
Ws = 2.518 + 0.0302En (MeV)
Vso= 4.199 (MeV)
r = 1.306, a = 0.452 (fm)
rs = 1.124, b = 0.690 (fm)
rso= 1.010, aso= 0.750 (fm).
the coupling scheme
ground state 0.0 MeV (0+)
1 phonon state 2.230 MeV (2+), 5.006 MeV (3-)
2 phonon state 3.779 MeV (0+), 4.280 MeV (2+)
4.459 MeV (4+)
coupling constants beta-2 = 0.30
beta-3 = 0.25
*********************************************************
mt=16(n,2n), 22(n,n'a), 28(n,n'p), 103(n,p), 107(n,a)
Based on the statistical model calculations with gnash
code/9/, without the precompound reaction correction.
transmission coefficients for proton and alpha particles
are calculated by using the omp of Becchetti-Geenlees
/10/ and Huizenga-Igo/11/, respectively.
Level density parameters are based on built-in values.
mt=103 (n,p) cross section
Adjusted to reproduce R. Ricamo data above 14 MeV /12/.
mf=4 Angular distributions of secondary neutrons
mt=2 Calculated with optical model (casthy).
mt=51-56 Calculated with coupled-channel statistical model
mt=16,22,28 Isotropic in the laboratory system.
mt=91 Isotropic distributions in cm were converted to
the distributions in lab.
mf=5 Energy distributions of secondary neutrons
mt=16,22,28,91,103,107 evaporation spectra,
mf=12 Photon production multiplicities
mt=16,22,28,103,107
Multiplicities were calculated by using the egnash code
/13/.
mt=102
Multiplicities were calculated by using the casthy code
/2/.
mt=51-56
Transition probability arrays were given.
mf=14 Photon angular distributions
mt=16,22,28,51-56,91,102,103,107
Isotropic
mf=15 Continuous photon energy spectra
mt=16,22,28,103,107
Multiplicities were calculated by using the egnash code
/13/.
mt=102
Multiplicities were calculated by using the casthy code
/2/.
References
1) Mughabghab,S.F. et al.: Neutron cross section, Vol.1 (1981).
2) Igarasi,S.: J. Nucl. Sci. Tech. 12, 67 (1975).
3) Fu,C.Y.: Atom. Data and Nucl. Data Tables. 17, 127 (1976).
4) Petitt,G.A. et al.: Nucl. Phys. 79, 231 (1960).
5) Virdis,A.: CEA-R-5144 (1981).
6) Lindholm,A. et al.: Nucl. Phys. A279, 445 (1977).
7) Leder,C.M. et al.: Table of Isotopes. 7th edit.
8) Asano et al.: private communication.
9) Young,P.G. and Arthur,E.D.: LA-6947 (1977).
10) Becchetti,Jr. and Greenlees,G.W.: Polarization phenomena
in nuclear reactions, p.682 (1971).
11) Huizenga,Jr. and Igo,G.J.: Nucl. Phys. 29, 462 (1962).
12) Ricamo, R. : NC 8, 383 (1951).
13) Yamamuro, N.: JAERI-M 90-006 (1990).