82-Pb-206
82-PB-206 JAERI EVAL-JUL87 M.MIZUMOTO
DIST-MAR02 REV3-SEP01 20010907
----JENDL-3.3 MATERIAL 8231
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 Newly evaluated for JENDL-3 by M.Mizumoto (jaeri)
87-11 Revise is recommended.
89-09 Revision is completed.
Compilation is made by T.Narita and T.Fukahori (jaeri)
94-04 JENDL-3.2.
mf2: Reich-Moore formula adopted.
mf3, 4, 5: By adopting the data from JENDL fusion file
mf12,15: Modified by K.Shibata(jaeri)
Compiled by T.Nakagawa (ndc/jaeri)
***** modified parts for JENDL-3.2 ********************
(3,4), (3,16). (3,17), (3,22), (3,28), (3,51-91)
(4,16-91), (5,16-91)
These data were taken from JENDL fusion file.
(2,151) Reich-Moore formula adopted
(3,102) Renormalized
(3,2)
(12,102), (15,102) Calculated with casthy
***********************************************************
01-07 JENDL-3.3
Compiled by K.Shibata
***** modified parts for JENDL-3.3 ********************
(1,451) Updated.
(3,1) Re-calculated.
(3,2) Re-calculated.
(3,102) Revised above 1 MeV.
(3,251) Deleted.
(4,2) Transformation matrix deleted.
(4,16-91) Deleted.
(5,16-91) Deleted.
(6,16-91) Taken from JENDL fusion file.
(12,16),(12,91) Revised.
(15,16),(15,91) Revised.
***********************************************************
-------------------------------------------------------------
JENDL fusion file /1/ (as of Oct. 1993)
Evaluated by K.Kosako (nedac) and S.Chiba (ndc/jaeri)
Compiled by K.Kosako.
Data were taken from JENDL-3.1 except for the following:
- The inelastic scattering cross sections and angular
distributions of inelastically scattered neutrons (except
continuum inelastic) were calculated with casthy2y and
dwucky in sincros-ii system/2/ including contributions
from direct reactions.
- The (n,2n), (n,3n), (n,na) and (n,np) reaction cross
sections (mt=16, 17, 22, 28) were calculated by egnash2
in the sincros-ii. The (n,2n) cross section was
renormalized to experimental data.
- Energy distributions of secondary neutrons were replaced
with those calculated by egnash2. The ddx's of the
continuum neutrons were calculated by kumabe's systema-
tics /3/ using f15tob /1/. The precompound/compound
ratio was calculated by the sincros-ii code system.
- Optical-model, level density and other parameters used in
the sincros-ii calculation are described in ref./2/.
Level schemes were determined on the basis of ENSDF/4/.
-------------------------------------------------------------
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 Resonance parameters
mt=151 Resolved resonance parameters for reich-moore formula
Resonance range: 1.0e-5 eV to 500 keV
Parameters were evaluated from the data of Horen+79 /5/, and
Mizumoto+79 /6/. Values of radiative width were taken from
ref./7/. Effective scattering radius of 8.042 fm and dummy
resonances at -4 and 8 MeV were adopted from ref./5/.
calculated 2200-m/s cross sections and res. integrals.
2200 m/s res. integ.
elastic 10.035 b -
capture 0.0306 b 0.1108 b
total 10.066 b -
mf=3 Neutron cross sections
Below 500 keV
No background cross sections are given.
Above 500 keV
Cross sections for JENDL-3.1 were obtained from optical and
statistical model calculations. The optical potential
parameters were obtained by fitting average total cross section
of natural lead:
V=47.0 - 0.250*E, Ws = 2.30 + 0.41*E, Vso = 6.0 (MeV)
r0 = 1.25 , rs = 1.30 , rso = 1.30 (fm)
a0 = 0.65 , b=0.48 , as0 = 0.689 (fm)
Level density parameters were determined using low-lying level
data and observed neutron resonance spacing.
For JENDL-3.2, the (n,2n), (n,3n), (n,na), (n,np) and inelastic
scattering cross sections were adopted from JENDL fusion file.
They were calculated with sincros-ii system/2/ by adopting
Walter-Guss omp modified by Yamamuro/2/ for neutron, Perey omp
/8/ for proton, Lemos omp modified by Arthur and Young/9/ for
alpha, Lohr-Haeberli omp/10/ for deuteron, Becchettii-Greenlees
omp/11/ for triton and he-3, and standard level density
parameters of sincros-ii system.
The data of total, capture, (n,p), (n,d) and (n,a) cross
sections are the same as JENDL-3.1.
mt=1 Total
Calculated with optical and statistical mode code casthy /12/
mt=2 Elastic scattering
(total)-(all other partial cross sections)
mt=4,51-65.91 Inelastic scattering
The cross sections were taken from JENDL fusion file. The level
scheme was adoptted from ref./4/ Contributions of the direct
process were calculated for the levels marked with '*', using
deformation parameters compiled by Raman et al./13/ and
spear/14/.
no. energy(MeV) spin-parity (direct process)
g.s. 0.0 0.0 +
1 0.8031 2.0 + *
2 1.1650 0.0 +
3 1.3405 3.0 + *
4 1.467 2.0 +
5 1.6841 4.0 + *
6 1.703 1.0 +
7 1.784 2.0 + *
8 1.9977 4.0 + *
9 2.149 2.0 +
10 2.2002 7.0 - *
11 2.315 0.0 +
12 2.379 4.0 +
13 2.3842 6.0 -
14 2.3914 4.0 +
15 2.424 2.0 +
Levels above 2.424 MeV were assumed to be continuum. The
direct inelastic scattering cross sections were calculated for
the levels at 2.648, 3.014, 3.774, 4.114, 4.33, 5.261, 6.103
and 6.187 MeV, and added to mt=91.
mt=16, 17, 22, 28 (n,2n), (n,3n), (n,na), (n,np)
Adopted from JENDL fusion file. Theoretical calculation was
made with sincros-ii. The (n,2n) cross section was adjusted to
reproduce the measured enargy spectra/15/ (factor = 1.2). The
data of Simakov et al. /16/ were also taken into consideration.
mt=102 Capture
Calculated with casthy /12/, and normalized to 0.0085 b at at 50
keV which was an average value obtained from the resonance
parameters.
For JENDL-3.3, the direct and semi-direct component was
calculated by using the method of Benzi and Reffo /19/ and added
to the JENDL-3.2 cross sections.
mt=103 (n,p)
Calculated with gnash /17/ and normalized to 2.0 mb at 14.5 MeV
by Belovickij+76 18/.
mt=107 (n,a)
Calculated with gnash /17/ and multiplied by 5.
mt=203 Total proton production
Sum of mt=28 and 103.
mt=207 Total alpha production
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2
Calculated with casthy /12/.
mt=51-65
Taken from JENDL fusion file. Calculated with the casthy and
dwucky in the sincros-ii system.
mf=6 Energy-angle distributions of secondary particles
mt=16, 17, 22, 28, 91, 203, 207
Taken from JENDL fusion file.
mf=12 Gamma-ray multiplicity produced by neutron reactions
mt=16,17,22,28,91,103,107
Calculated with gnash /17/.
Data of mt=16,91 were revised.
mt=51-65
Transition probabilities are given.
m=102
Calculated with casthy /12/. Multiplicity of a line spectrum
at thermal is 1.0.
mf=14 Angular distributions of secondary gamma-rays
mt=16,17,22,28,51-65,91,102,103,107 : assumed isotropic.
mf=15 Energy distribution of secondary gamma-rays
mt=16,17,22,28,91,107
Calculated with the gnash /17/.
Data of mt=16,91 were revised.
m=102
Calculated with casthy /12/. At thermal, a line spectrum of
6.73835 MeV was assumed.
References
1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).
2) Yamamuro, N.: JAERI-M 90-006 (1990).
3) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).
4) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.
5) Horen, D.J. et al.: Phys. Rev. C20, 478 (1979).
6) Mizumoto, M. et al.: Phys. Rev. C19 ,335 (1979).
7) Mughabghab, S.F.: Neutron Cross Sections, Vol.1 part B
Academic Press (1984).
8) Perey, F.G.: Phys. Rev., 131, 745 (1963).
9) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).
10) Lohr, J.M. and Haeberli, W.: Nucl. Phys., A232, 381 (1974).
11) Becchetti, F.D. Jr. and Greenlees, G.W.: "Polarization
Phenomena in Nucl. Reactions," Univ. Wisconsin Press, p.682
(1971).
12) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).
13) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1
(1987)
14) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).
15) Takahashi, A. et al.: JAERI-M 86-080, 393 (1986).
16) Simakov, S.P. et al: Workshop on Nucl. Data for Fusion Reactor
Technol., Del Mar, March 3-6 (1993).
17) Young, P.G. and Arthur, E.D.: LA-6974 (1977).
18) Belovickij et al.: 75 Kiev, 4, 209 (1976).
19) Benzi, V. and Reffo, G.:CCDN-NW/10 (1969).