15-P - 31
15-P - 31 FUJI E.C. EVAL-MAY87 H.NAKAMURA
DIST-MAR02 REV3-JUL01 20010726
----JENDL-3.3 MATERIAL 1525
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-05 Newly evaluated by H.Nakamura (fuji electric co.ltd)
93-12 JENDL-3.2
Total cross section was recalculated by T.Watanabe. (khi)
Gamma-ray production cross sections were evaluated by
T. Asami (de).
***** modified parts for JENDL-3.2 ******************************
(3,1) A new omp set was determined.
(3,2) total - nonelastic
(3,107) Q-value corrected
mf=12,13,14,15 newly evaluated
******************************************************************
01-07 (3,103) revised.
Compiled by K.Shibata (jaeri) for JENDL-3.3
****** modified parts for JENDL-3.3 *********************
(1,451) Updated.
(3,1) Re-calculated.
(3,2) Re-calculated.
(3,103) Taken from JENDL Dosimetry File 99
(3,251) Deleted.
(4,2) Transformation matrix deleted.
(5,16-91) INT=22
***********************************************************
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 - 500 keV
Parameters are taken from BNL 325 4th edition/1/, and
Macklin et al./2/.
Cross sections calculated with these parameters were
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 3.134 b - /1/
capture 0.166 b 0.081 b /1/
total 3.300 b -
mf=3 Neutron cross sections
Below 500 keV
background cross section.
mt=1,2 0.07029 b
Above 500 keV
mt=1 New optical model calculation using the parameter
set determined by T. Watanabe
V = 50.58 - 0.06476E (MeV)
Ws = 6.583 + 0.5927E (MeV)
Vso= 3.391 (MeV)
r = 1.36, a = 0.422(fm)
rs= 1.23, b = 0.517(fm)
rso=0.938, aso=0.600(fm)
mt=2 total - nonelastic
mt=4,51-56,91,102 Total, elastic, inelastic and capture
Calculated with casthy code/3/, considering the
competition with the threshold reaction channels.
Optical potential parameters of Fu/4/ are adjusted
to reproduce the following experimental data:
mt=1 total NESTORr data (many authors)
mt=2 elastic -
mt=4 inelastic -
The spherical optical potential parameters:
V=43.0 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 1.8 mb at 500 keV
based on (7 mb at 30 keV) by Macklin et al./5/.
The discrete level scheme taken from ref./6/:
no. energy (MeV) spin-parity
(g.s.) 0.0 1/2 -
1 1.266 3/2 +
2 2.234 5/2 +
3 3.134 1/2 +
4 3.295 5/2 +
5 3.415 7/2 +
6 3.506 3/2 +
Continuum levels assumed above 4.0 MeV. The level
density parameters of Asano et al. /7/ are used.
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 /8/, without the precompound reaction correction.
Transmission coefficients for proton and alpha particle
are calculated by using the omp of Becchetti-Greenlees
/9/ and Huizenga-Igo/10/, respectively. In the cases of
mt=103 and 107, the experimental data were also
considered together with the calculations.
Level density parameters are based on built-in values.
***** For JENDL-3.3 *************************************
The (n,p) reaction cross section was taken from JENDL
Dosimetry File 99 (JENDL/D-99). The evaluation is based
on the experimental data /12-24/ and nuclear model
calculation by Strohmaier/25/.
***********************************************************
mf=4 Angular distributions of secondary neutrons
mt=2 Calculated with optical model(casthy).
mt=51-56 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 Evaporation spectra.
mf=12 Photon production multiplicity
mt=102,103,107 Calculated by sincros-ii/11/.
mf=13 Photon production cross section
mt=3 Calculated by sincros-ii/11/.
mt=4 Discrete lines calculated by taking
account of branching ratios
mf=14 Photon angular distribution
mt=3,4,102,103,107 Isotropic
mf=15 Photon energy distribution
mt=3,103,107 Calculated by sincros-ii/11/.
mt=102 Calculated by casthy/3/.
References
1) Mughabghab, S.F. et al.: Neutron Cross Section, Vol.1 (1981).
2) Macklin, R.L. et al.: Phys. Rev. C32, 379 (1985).
3) Igarasi, S.: J. Nucl. Sci. Tech. 12, 67 (1975).
4) Fu, C.Y.: Atom. Data and Nucl. Data Tables. 17, 127 (1976).
5) Macklin, R.L. et al.: Phys. Rev. 129, 2695 (1963).
6) Lederer, C.M. et al.: Table of Isotopes. 7th edit.
7) Asano et al.: private communication.
8) Young, P.G. and Arthur, E.D.: LA-6947 (1977).
9) Beccheti, Jr. and Greenless, G.W.: Polarization Phenomena
in Nuclear Reactions, p.682 (1971).
10) Huizenga, Jr. and Igo, G.J.: Nucl. Phys. 29, 462 (1962).
11) Yamamuro, N.: JAERI-M 90-006 (1990).
12) Metzger, F. et al.: Helvetica Physica Acta, 21, 278 (1948).
13) Ricamo, R. et al.: Nuovo Cimento, 8, 383 (1951).
14) Forbes, S.G.: Phys. Rev, 88, 1309 (1952).
15) Paul, E.B. et al.: Can. J. Phys., 31, 267 (1953).
16) Grundl, J.A. et al.: Phys. Rev., 109, 425 (1958).
17) Cuzzocrea, P. et al.: Nuovo Cimento, 16, 450 (1960).
18) Kantele, J. et al.: Nucl. Phys., 35, 353 (1962).
19) Grimeland, B. et al.: Phys. Rev. B137, 878 (1965).
20) Paulsen, A. et al.: Proc. 1st. IAEA Conf. on Nuclear Data for
Reactors, Paris, France, 17-21 Oct 1996, p.217 (1966).
21) Grundl, J.A. : Nucl. Sci. Eng., 30, 39 (1967).
22) Schantl, W. : Dissertation (1980).
23) Robertson, J.C. et al.: J. Nucl. Energy, 27, 531 (1973).
24) Aleksandrov, D.V. et al.: Atomnaya Energuya, 39, 137 (1975).
25) Strohmaier, B. et al.: Physik Daten, 13-2 (1980).