82-Pb-207
82-PB-207 JAERI EVAL-JUL87 M.MIZUMOTO
DIST-MAR02 REV3-SEP01 20010907
----JENDL-3.3 MATERIAL 8234
-----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.
Resonance parameters corrected by T.Nakagawa
Data for mf=3,4,5 were adopted from JENDL fusion file
Gamma-ray production data 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, and upper boundary
of resonance region was changed from 500 to 475 keV
(3,102) Renormalized
(3,107) 0 at 500 keV was inserted
(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 ranges: 1.0e-5 eV to 475 keV
Parameters were based on the data of Horen+78 /5/ and recommen-
dation of Mughabghab/6/ parameters of dummy resonances were
taken from ENDF/B-VI evaluation/7/. Average radiative width of
0.11 eV was used for the resonances whose value was unknown.
Effective scattering radius of 9.53 fm was determined to
reproduce well the experimental data of total cross section.
calculated 2200-m/s cross sections and res. integrals.
2200 m/s res. integ.
elastic 11.254b -
capture 0.7120 b 0.3911 b
total 11.966 b -
mf=3 Neutron cross sections
Below 475 keV
No background cross sections are given.
Above 475 keV
Cross sections for JENDL-3.1 were obtained with optical and
statistical model code casthy /8/. 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
/9/ for proton, Lemos omp modified by Arthur and Young/10/ for
alpha, Lohr-Haeberli omp/11/ for deuteron, Becchettii-Greenlees
omp/12/ for triton and he-3, and standard level density
parameters of sincros-ii system.
mt=1 Total
Calculated with casthy /8/.
mt=2 Elastic scattering
(total)-(all other partial cross sections)
mt=4,51-58,91 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 '*'.
no. energy(MeV) spin-parity (direct process)
g.s. 0.0 1/2 -
1 0.5697 5/2 - *
2 0.8977 3/2 - *
3 1.6334 13/2 +
4 2.3399 7/2 - *
5 2.6232 5/2 + *
6 2.6624 7/2 +
7 2.7030 7/2 +
8 2.7280 9/2 +
Levels above 2.728 MeV were assumed to be continuum. The direct
inelastic scattering cross sections were calculated for the
levels at 3.384, 3.509, 3.583, 3.62, 3.901, 4.103, 4.14, 4.19,
4.313, 4.364, 4.404, 4.627, 5.081, 5.352 and 6.188 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/13/ (factor = 1.2). The
data of Simakov et al. /14/ were also taken into consideration.
mt=102 Capture
Calculated with casthy /8/ and normalized to a 30 keV
Maxwellian spectrum average of 0.011 b/15/.
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 /16/ and normalized to 1.6 mb at 14.5 MeV
by Belovickij+76 /17/
mt=107 (n,a)
Calculated with gnash /16/ 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 /5/.
mt=51-58
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 /18/.
Data of mt=16,91 were revised.
mt=51-58
Transition probabilities are given.
m=102
Calculated with casthy /5/. Multiplicity of a line spectrum
at thermal is 1.0.
mf=14 Angular distributions of secondary gamma-rays
mt=16,17,22,28,51-58,91,102,103,107 : assumed isotropic.
mf=15 Energy distribution of secondary gamma-rays
mt=16,17,22,28,91,107
Calculated with the gnash /18/.
Data of mt=16,91 were revised.
m=102
Calculated with casthy /5/. At thermal, a line spectrum of
7.36735 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. C18, 722 (1978)
6) Mughabghab, S.F.: Neutron Cross Sections, vol.1, part B,
Academic Press (1984).
7) Fu, C.Y. et al.: BNL-NCS-17541(ENDF-201), p.336 (1991).
8) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).
9) Perey, F.G.: Phys. Rev., 131, 745 (1963).
10) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).
11) Lohr, J.M. and Haeberli, W.: Nucl. Phys., a232, 381 (1974).
12) Becchetti, F.D. Jr. and Greenlees, G.W.: "Polarization
Phenomena in Nucl. Reactions," Univ. Wisconsin Press, p.682
(1971).
13) Takahashi, A. et al.: JAERI-M 86-080, 393 (1986).
14) Simakov, S.P. et al: Workshop on Nucl. Data for Fusion Reactor
Technol., Del Mar, March 3-6 (1993).
15) Allen, B.J. et al. : Phys. Rev., C8, 1504 (1973).
16) Young, P.G. and Arthur, E.D. : LA-1974 (1977)
17) Belovickij et al. : 75 Kiev, 4, 209 (1976)
18) Lederer, C.M. and shirley V.S.: Table of Isotopes, 7th ed.
19) Benzi, V. and Reffo, G.:CCDN-NW/10 (1969).