13-Al- 27
13-AL- 27 TIT,JAERI EVAL-MAR88 Y.HARIMA,H.KITAZAWA,T.FUKAHORI
88MITO, 473 DIST-MAR02 REV3-JUL01 20010713
----JENDL-3.3 MATERIAL 1325
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-03 Evaluation was performed for JENDL-3 by Harima, Kitazawa
(Tokyo Institute of Tech.) and Fukahori (jaeri). Details
are given in ref./1/.
88-03 Compiled by Fukahori.
93-12 JENDL-3.2.
Compiled by T.Nakagawa (ndc/jaeri)
***** Modified parts for JENDL-3.2 ********************
(3,2)
(3,66-91) Taken from JENDL fusion file*
(3,4), (3,51-70) Cross-section curves were smoothed.
(4,16-28), (4,91) Taken from JENDL fusion file
(5,16-91) Taken from JENDL fusion file
(12,51-70), (12,102)
***********************************************************
-------------------------------------------------------------
JENDL fusion file /2/ (as of Sep. 1993)
Evaluated by B.Yu (ciae) and S.Chiba (ndc/jaeri)
Compiled by B.Yu.
Cross sections were mainly taken from JENDL-3.1, except
for the (n,n') (mt=66 to 70) and (n,n') continuum (mt=91)
reactions which were taken from the calculation with
sincros-II/3/. Angular distributions of these levels
were taken to be equal to that of mt=66 in JENDL-3.
EDXs for mt=16, 22, 28 and 91 were replaced by the
sincros-II calculation. mf=6 were created by f15tob
program. Kumabe's systematics/4/ was used. The pre-
compound/compound ratio was taken from the sincros-II
calculation.
Optical-model, level density and other parameters used
in the sincros-II calculation are described in ref./3/.
Level schemes were determined on the basis of ENDSF/5/.
-------------------------------------------------------------
00-10 Re-evaluated by K. Shibata (jaeri) for JENDL-3.3
Compiled by K. Shibata
***** Modified parts for JENDL-3.3 ***************************
(1,1451) Updated
(3,1),(3,2),(3,4) Re-calculated.
(3,16) Yamamuro's calculations /15/
(3,61),(3,62),(3,63) DWBA calculations were added.
(3,67),(3,70) DWBA calculations were added.
(3,203),(3,207) Calcualted.
(3,251) Deleted.
(4,2) Transformation matrix deleted.
(4,16),(4,22),(4,28) Deleted.
(4,91) Deleted.
(5,16-91) Deleted.
(6,16-91) Taken from JENDL fusion file.
***************************************************************
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 Resonance parameters:
mt=151
Resolved resonances : 1.0e-5 eV - 0.21 MeV
The resonance parameters were searched, using MLBW formula/6/.
An initial guess of the parameters search was taken from ref.
/7/.
Calculated 2200-m/s cross sections and resonance integrals
2200-m/sec res. integ.
elastic 1.414 b -
capture 0.231 b 0.123 b
total 1.645 b -
mf=3 Neutron cross sections
mt=1 Total cross section
Between 0.21 and 20 MeV, the cross sections were obtained by
an eye-guide so as to follow the experimental data.
mt=2 Elastic scattering cross sections
Obtained by subtracting partial cross sections from the
total cross sections.
mt=4,51-70,91 Inelastic scattering cross sections
For JENDL-3.1, cross sections up to 17-th level were calculated
with the statistical-model code casthy /8/ and the coupled-
channel model code ecis /9/ or jupitor-1 /10/, taking account
of competitive processes for neutron, proton, alpha-particle
and gamma-ray emission/1/. The following levels/11/ were
taken into account.
no. energy(MeV) spin-parity
g.s. 0.0 5/2 +
1. 0.8438 1/2 +
2. 1.0145 3/2 +
3. 2.2100 7/2 +
4. 2.7340 5/2 +
5. 2.9814 3/2 +
6. 3.0040 9/2 +
7. 3.6780 1/2 +
8. 3.9560 5/2 +
9. 4.0540 3/2 -
10. 4.4090 5/2 +
11. 4.5103 11/2 +
12. 4.5800 7/2 +
13. 4.8120 5/2 +
14. 5.1550 3/2 -
15. 5.2460 5/2 +
16. 5.4199 5/2 +
17. 5.4330 9/2 +
Continuum levels were assumed above 5.6 MeV. Level density was
calculated, using the Gilbert-Cameron formula. The level-
density parameters were obtained from a cumulative plot of
observed levels/1/.
For JENDL-3.2, cross sections for mt's from 66 to 70 and conti-
nuum inelastic were replaced with JENDL fusion file. These mt's
correspond to the following levels.
16. 5.4199 5/2 +
17. 5.4328 5/2 +
18. 5.4384 5/2 +
19. 5.4998 7/2 +
20. 5.5507 3/2 +
Above 5.6 MeV, cross sections were summed up as the continuum
inelastic (mt=91).
Several energy points were added to mt= 4, 51-70 in order to
smooth their cross section curves.
For JENDL-3.3, the direct process was considered /16/ by DWBA
calculations for mt=61,62,63,67,70.
mt=16 (n,2n) cross sections
Re-calculated by the sincros-II code /17/.
mt=22 (n,na) cross sections
Calculated by the statistical model with the gnash code/1,12/.
optical potential for alpha-particles was determined, using
the dispersion theory /13/.
mt=28 (n,np) cross sections
Calculated by the statistical model with the gnash code/1,12/.
mt=102 capture
Calculated with the statistical-model code casthy/8/ and the
direct-semidirect-model code hikari/14/. The statistical-
model calculations were normalized to 0.6 mb at 0.6 MeV.
mt=103 (n,p) cross sections
Calculated by the statistical model with the gnash code/1,12/.
mt=107 (n,a) cross sections
Obtained by an eye-guide to follow observed values /15/.
mt=111 (n,2p) cross sections
Calculated by the statistical model with the gnash code/1,12/.
mt=203 proton production
Sum of mt=28 and 103.
mt=207 alpha production
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2
Calculated with the statistical-model code casthy /1,8/.
mt=51-66
Incoherent sum of the statistical model and coupled-channel
model calculations/1/. Calculated with casthy and ecis or
jupitor-1.
mt=67-70
Assumed to be the same as mt=66.
mf=6 Energy-angle distributions of secondary particles
mt=16,22,28,91,203,207
Taken from JENDL fusion file.
mf=12 gamma-ray multiplicities (below 5.80993 MeV)
mt=51-70
Multiplicities were calculated from transition probabilities.
mt=102
Calculated from energy balance.
mt=103,107
Calculated by using the gnash code/1,12/.
mf=13 Gamma-ray production cross sections (above 5.80993 MeV)
mt=3
Calculated by the statistical model and coupled-channel model,
using the gnash code /12/ and the ecis /9/ or jupitor-1 code
/10/. Branching ratios for transitions between discrete levels
were taken from ref./3/. Gamma-ray transition strength in the
continuum was calculated by the brink-axel giant resonance
model for E1 transition and by the Weisskopf single-particle
model for E2 and M1 transition/1/.
mf=14 Gamma-ray angular distributions
mt=3,51-70,102,103,107
Isotropic distribution was assumed.
mf=15 Gamma-ray spectra
mt=3,102,103,107
Calculated with the gnash code/1,12/
References
1) Kitazawa H. et al.: Proc. Int. Conf. Nuclear Data for
Science and Technology, Mito, 1988, p.473, (1988).
2) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).
3) Yamamuro N.: JAERI-M 90-006 (1990).
4) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990).
5) ENSDF: Evaluated Nuclear Stracture Data File.
6) Nakagawa T.: JAERI-M 84-192 (1984).
7) Mughabghab S.F. et al.: "Neutron Cross Sections, Vol. 1
Part A", Academic Press (1981).
8) Igarasi S. and Fukahori T.: JAERI 1321 (1991).
9) Raynal J.: Computer Program ECIS79 for Coupled-Channel
Calculations, 1979 (unpublished).
10) Tamura T.: Rev. Mod. Phys., 37, 679 (1965).
11) Endt P.M. and Van der Leun C.: Nucl. Phys., A310, 1 (1978).
12) Young P.G. and Arthur E.D.: LA-6947 (1977).
13) Kitazawa H. et al.: unpublished.
14) Kitazawa H.: Computer Program Hikari for Direct-Semidirect
Capture Calculations, 1980 (unpublished).
15) Vonach H.: Nuclear Data Standards for Nuclear Measurements,
IAEA Technical Reports Series no. 227 (1983).
16) Shibata K.: Private communication (2000).
17) Yamamuro N.: Private communication (2000).