16-S - 33 FUJI E.C. EVAL-MAY87 H.NAKAMURA
DIST-MAY10 20090828
----JENDL-4.0 MATERIAL 1628
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
The data were taken from JENDL-3.3.
===========================================================
HISTORY
87-05 Newly evaluated by H.Nakamura (fuji electric co. ltd.)
94-02 JENDL-3.2
New optical model calculation was performed by T. Watanabe
(khi).
Data were compiled by K. Shibata (jaeri).
***** modified parts for JENDL-3.2 ******************
(3,1),(3,4),(3,51-57),(3,91),(3,251),(4,2),(4,51-57)
optical and statistical model 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 - 260 keV
Parameters are taken from BNL325 4th edition/1/, and
C.Wagemans and H.Weigmann/2/.
Cross sections calculated with these parameters are to
be corrected 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 2.84 b - /1/
capture 0.35 b 0.164 b /1/
total 3.36 b - -
mf=3 Neutron cross sections
Below 260 keV
Background cross sections are given for mt=1:
mt=1 0.171b : 0.002(n,p) + 0.169(n,a) b
mt=103 (n,p) 0.0016 b, based on 2200-m/s data /1/.
mt=107 (n,a) 0.169 b, same to the above.
Above 260 keV
mt=1,2,4,51-57,91,102
Total, elastic, inelastic and capture cross sections
calculated with casthy code /3/, considering the
competition with the threshold reaction channels.
Optical potential parameters of C.Y.Fu/4/ are adjusted
to reproduce the following experimental data:
mt=1 total -
mt=2 elastic cross sections of s-32.
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 0.5 mb at 260 keV
based on s-32 capture cross sections.
The discrete level scheme taken from ref./5/:
no. energy(MeV) spin-parity
(g.s.) 0.0 3/2 +
1 0.8404 1/2 +
2 1.966 5/2 +
3 2.313 3/2 +
4 2.866 5/2 +
5 2.934 7/2 -
6 2.969 7/2 +
7 3.220 3/2 -
Continuum levels are assumed above 3.6MeV. The level
density parameters of Asano et al./6/ are used.
***** JENDL-3.2 ****************************************
mt=1,4,51-57,91,251
Optical and statistical model calculation
was performed by using the omp set given as follows:
V = 58.83 - 0.5635En (MeV)
Ws = 3.609 + 0.1819En (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).
*********************************************************
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 /7/, without the precompound reaction correction.
Transmission coefficients for proton and alpha particles
are calculated by using the omp of becchetti-geenlees/8/
and huizenga-igo/9/, respectively.
Level density parameters are based on built-in values.
mf=4 Angular distributions of secondary neutrons
mt=2 Calculated with optical model (casthy).
mt=51-57 Calculated with hauser-feshbach formula (casthy)
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
/10/.
mt=102
Multiplicities were calculated by using the casthy code
/3/.
mt=51-57
Transition probability arrays were given.
mf=14 Photon angular distributions
mt=16,22,28,51-57,91,102,103,107
Isotropic
mf=15 Continuous photon energy spectra
mt=16,22,28,103,107
Multiplicities were calculated by using the egnash code
/10/.
mt=102
Multiplicities were calculated by using the casthy code
/3/.
References
1) Mughabghab, S.F. et al.: Neutron cross section, Vol.1 (1981).
2) Wagemans, C. and Weigman, H.: Grenoble-conf., 462 (1981).
3) Igarasi, S.: J. Nucl. Sci. Tech., 12, 67 (1975).
4) Fu, C.Y.: Atom.Data and Nucl. Data Tables, 17, 127 (1976).
5) Ledrer, C.M. et al.: Table of isotopes. 7th edit.
6) Asano et al.: private communication.
7) Young, P.G. and Arthur, E.D.: LA-6947 (1977).
8) Becchetti, Jr. and Greenlees, G.W.: Polarization phenomena
in nuclear reactions, p.682 (1971).
9) Huizenga, Jr. and Igo, G.J.: Nucl. Phys., 29, 462 (1962).
10) Yamamuro, N.: JAERI-M 90-006 (1990).