72-Hf-180
72-HF-180 NAIG+ EVAL-JUL89 HIDA, YOSHIDA AND SHIBATA(JAERI)
DIST-MAR02 REV3-APR01 20010417
----JENDL-3.3 MATERIAL 7243
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
89-07 New evaluation for JENDL-3 was made by K.Hida, T.Yoshida
(naig) and K.Shibata (jaeri).
94-01 JENDL-3.2.
Compiled by T.Nakagawa (ndc/jaeri)
***** modified parts for JENDL-3.2 ********************
(3,2), (3,4), (3,51-52), (3,56-61)
Curves of inelastic scattering cross sections
were smoothed by adding interpolated values at
several energy points.
***********************************************************
01-04 JENDL-3.3
Compiled by K.Shibata (ndc/jaeri)
***** modified parts for JENDL-3.3 ********************
(1,451) Updated.
(3,1) Mesured data were considered between 110 keV
and 7.5 MeV.
(3,2) Re-calculated.
(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 Resonance parameters
mt=151 Resolved and unresolved resonance parameters
Resolved resonances for MLBW formula
Energy range : 1.0e-5 eV to 2.5 keV
Res. energies and gam-n : BNL-325 /1/. If unknown, gam-n is
calculated from d-obs and s0, and in
this case, gam-gamma from
(gam-n)*(gam-gamma)/(gam-total).
Gam-gamma : 0.050 eV assumed if unknown.
Radius : 8.0 fm
Unresolved resonances
Energy range : 2.5 keV to 50 keV.
s0, s1,r and gam-gamma : Adjusted so that the calculated total
and capture cross sections were
reproduced well.
Results are d-obs = 158 eV, s0 = 1.90e-4, s1 = 0.44e-4,
r = 8.5 fm and gam-gamma = 0.05 eV.
2200 m/sec cross sections and calculated res. integrals.
2200 m/sec res. integ.
total 34.2 b -
elastic 21.2 b -
capture 13.0 b 34.0 b
mf=3 Neutron cross sections
Below 50 keV :
No background was given.
Above 50 keV :
mt=1,2,4,51-61,91,102 Total,elastic,inelastic and capture
Calculated with ecis /2/ and casthy /3/. Deformed optical
potential for ecis calculation was determined so as to
reproduce the experimental total cross section of natural
hafnium, starting with the Haouat potential /4/.
V0 = 46.60-0.3*En, Ws = 3.70+0.4*En (En<10), Vso = 6.2 (MeV),
7.70 (En>10)
a0 = 0.63, as = 0.52, aso = 0.47 (fm),
r0 = 1.24, rs = 1.24, rso = 1.12 (fm),
beta-2 = 0.256, beta-4 = 0.0.
The deformation parameter beta-2 was determined from the
measured e2 transition probability data /5/. The lowest three
levels belonging to the ground state rotational band were
coupled in the calculation. The spherical optical potential
for casthy calculation is the same as that of JENDL-2.
V0 = 38.0, Ws = 8.0+0.5*sqrt(En), Vso = 7.0 (MeV),
a0 = 0.47, as = 0.52 , aso = 0.47 (fm),
r0 = 1.32, rs = 1.32 , rso = 1.32 (fm).
Capture cross section was normalized to the measured data of
beer et al. /6/ at 30 keV. Competing processes (n,2n), (n,3n),
(n,p), and (n,alpha) were calculated with gnash /7/ and fed to
ecis-casthy calculation. The level fluctuation and interference
effects were considered. Level scheme was taken from table of
isotopes /8/.
no. energy(MeV) spin-parity
g.s. 0.0 0 +
1 0.09332 2 +
2 0.3086 4 +
3 0.6409 6 +
4 1.0839 8 +
5 1.1416 8 -
6 1.1832 4 +
7 1.1997 2 +
8 1.2910 4 +
9 1.3744 3 -
10 1.4092 4 +
11 1.5393 3 -
Continuum levels assumed above 1.6076 MeV.
The level density parameters for Gilbert and Cameron's formula
/9/ are the same as those of JENDL-2.
a(1/MeV) c(1/MeV) t(MeV) Ex(MeV) sigma**2
hf-180 21.37 2.35 0.519 5.42 7.64
hf-181 21.91 6.47 0.479 4.08 4.88
*** modification for JENDL-3.3 ********************************
For mt=1, measured data /10,11,12/ on natural element were
considered in the energy region from 110 keV to 7.5 MeV.
****************************************************************
mt=16,17,103,107 (n,2n), (n,3n), (n,p) and (n,alpha)
Calculated with gnash /7/. The transmission coefficients for
the incident channel were generated with ecis /2/, while those
for the exit channels with eliese-3 /13/. The preequilibrium
parameter f2 was f2=5.0.
mf=4 Angular distributions of secondary neutrons
mt=2,51-61,91
Calculated with ecis /2/ and casthy /3/.
mt=16,17
Isotropic in the laboratory system.
mf=5 Energy distributions of secondary neutrons
mt=16,17,91
Calculated with gnash /7/.
mf=12 Photon multiplicities and transition probabilities
mt=16,17,91,102,103,107
Calculated with gnash /7/ and stored under option-1 (photon
production multiplicities). The photon strength functions for
most nuclei were taken from /1/, while those for some hafnium
isotopes were determined from capture cross section normaliza-
tion to the experimental data. The photon profile function is
a superposition of the berman-type giant dipole resonance /14/
and the pygmy resonance whose parameter values were cited from
the neighbouring nucleus Ta /15/.
eg1 = 15.23, eg2 = 12.3 , ep = 5.2 (MeV),
gg1 = 4.48, gg2 = 2.43, gp = 2.5 (MeV),
sig-pygmy/sig-gdr = 0.0245.
mt=51-61
Stored under option-2 (transition probability array). Data were
taken from /8/.
mf=14 Photon angular distributions
mt=16,17,51-61,91,102,103,107
Isotropic.
mf=15 Continuous photon energy spectra
mt=16,17,91,102,103,107
Calculated with gnash /7/.
References
1) Mughabghab S.F.: Neutron cross sections, Vol.1, Part B (1984).
2) Raynal J.: IAEA SMR-9/8 (1970).
3) Igarasi S. and Fukahori T.: JAERI 1321 (1991).
4) Haouat G. et al.: Nucl. Sci. Eng., 81, 491 (1982).
5) Raman S. et al.: At. Data Nucl. Data Tables, 36, 1 (1987).
6) Beer H. and Macklin R.L.: Phys. Rev., C26, 1404 (1982).
7) Young P.G. and Arthur E.D.: LA-6947 (1977).
8) Lederer C.M. and Shirley V.S.: Table of isotopes 7th edition
(1979).
9) Gilbert A. and Cameron A.G.W.: Can. J. Phys., 43, 1446 (1965).
10) Sherwood G.L. et al.: Nucl. Sci. Eng., 39, 67 (1970).
11) Foster,Jr. D.G. and Glasgow D.W.: Phys. Rev., C3, 576 (1971).
12) Poenitz W.P. and Whalen J.F.: ANL/NDM-80 (1983).
13) Igarasi S.: JAERI-1224 (1972).
14) Berman B.L.: At. Data Nucl. Data Tables, 15, 319 (1975).
15) Igashira M. et al.: Int. Symp. Capture Gamma-ray Specroscopy
and Related Topics - 1984, 523 (1985).