Back
19-K - 39 FUJI E.C. EVAL-MAY87 H.NAKAMURA
DIST-JAN09 20090105
----JEFF-311 MATERIAL 1925
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
******************************************************************
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JENDL-3.3 **
** **
******************************************************************
HISTORY
87-05 Newly evaluated by H.Nakamura (fuji electric co. ltd.)
94-02 JENDL-3.2
Total cross section was calculated by T. Watanabe (khi).
Inelastic scattering cross sections were calculated by
K.Shibata (jaeri).
Data were compiled by K.Shibata.
***** modified parts for JENDL-3.2 ****************************
(3,1),(3,4),(3,51-91),(3,251),(4,2),(4,51-54)
new optical and statistical model cal.
(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 - 200 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 integlals
2200-m/sec res.integ. ref.
elastic 2.06 b - -
capture 2.10 b 1.1 b /1/
total 4.16 b - -
mf=3 Neutron cross sections
Below 200 kev
Background data for mt=1 : (mt=107)-cross sections.
mt=107 (n,a)=0.04 b (10**-5 eV), 0.0043 b (2200m/s)/1/,
int=5.
Above 200 keV
mt=1,2,4,51-54,91,102 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 used.
The spherical optical potential parameters:
V = 46.72 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 4.2 mb at 200 keV.
The discrete level scheme taken from ref./4/:
no. energy(MeV) spin-parity
(g.s) 0.0 3/2 +
1 2.523 1/2 +
2 2.814 7/2 -
3 3.019 3/2 -
4 3.598 9/2 -
Continuum levels assumed above 3.8 MeV. The level
density parameters of Asano et al./5/ are used.
***** JENDL-3.2 ********************************************
The total and inelastic scattering cross sections were cal-
culated by using the omp set determined by T. Watanabe.
V = 54.36 - 0.325En (MeV)
Ws= 2.258 + 0.1698En (MeV)
Vso=3.341 (MeV)
r =1.20 ,a =0.658 (fm)
rs =1.32 ,b =0.602 (fm)
rso=1.10 ,aso=0.406 (fm)
The cross sections of mt=16,22,28,103,107 in JENDL-3.1 were
considered as the competing process for the statistical model
calculation.
************************************************************
200 keV - 1.0 MeV
mt=107 (n,a)-cross section = 2.6*10**-5 b (constant):
assumed from the calculated value at 1.0 MeV.
Above 1.0 MeV
mt=16,22,28,103,107 (n,2n), (n,na), (n,np), (n,p), (n,a)
Based on the statistical model calculations with gnash
code/6/, without the precompound reaction correction.
transmission coefficients for proton and alpha particle
are calculated by using the omp of Becchetti-Greenlees
/7/ and Huizenga-Igo/8/, respectively.
Level density parameters are based on built-in values.
At the energy range of 4 - 20 MeV, (n,p) cross section
was based on the experimental data/9-11/.
mf=4 Angular distributions of secondary neutrons
mt=2 Calculated with optical model (casthy).
mt=51-54 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
/12/.
mt=102
Multiplicities were calculated by using the casthy code
/2/.
mt=51-54
Transition probability arrays were given.
mf=14 Photon angular distributions
mt=16,22,28,51-54,91,102,103,107
Isotropic
mf=15 Continuous photon energy spectra
mt=16,22,28,103,107
Multiplicities were calculated by using the egnash code
/12/.
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) Lederer, C.M. et al.: Table of isotopes. 7th edit.
5) Asano et al.: private communication.
6) Young, P.G. and Arthur, E.D.: LA-6947 (1977).
7) Becchetti, Jr. and Greenlees, G.W.: Polarization phenomena
in nuclear reactions, p.682 (1971).
8) Huizenga, Jr. and Igo, G.J.: Nucl. Phys., 29, 462 (1962).
9) Bass, R. et al.: Nucl. Phys., 56, 569 (1964).
10) Bormann, M. et al.: Zeitschrift f. Naturforschung, Section A,
15, 200 (1960).
11) Aleksandrov,D.V. et al.: Atomnaya Energiya, 39(2), 137 (1975).
12) Yamamuro, N.: JAERI-M 90-006 (1990).
Back
|
