64-Gd-154 JAEA+ EVAL-Dec09 N.Iwamoto,A.Zukeran,K.Shibata
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 6431
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-12 The resolved resonance parameters were evaluated by
A.Zukeran,K.Shibata.
The data above the resolved resonance region were evaluated
and compiled by N.Iwamoto.
MF= 1 General information
MT=451 Descriptive data and directory
MF= 2 Resonance parameters
MT=151 Resolved and unresolved resonance parameters
Resolved resonance region (MLBW formula) : below 2.76 keV
Resonance parameters below 486 eV were evaluated on the
basis of Mughabghab/1/. Above 486 eV, parameters were
adopted from Macklin/2/. For the resonances only whose
capture area was measured, neutron widths were determined
from the capture area and an average radiation width of
0.088 eV/1/. The total spin J and orbital angular
momentum L were assigned by considering the magnitude
of the capture area of each resonance. A negative resonance
was added so as to reproduce the thermal capture cross
section of 85+-12 barns/1/. Scattering radius of 8.0 fm
was estimated from an optical model calculation shown in
fig. 2 of ref./1/.
In JENDL-4, the data for 11.57 - 269.6 eV were replaced with
the ones obtained by Leinweber et al./3/ The energy of
the negative resonance was adjusted.
Unresolved resonance region : 2.76 keV - 300.0 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /4/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
CCOM /5/ and CCONE /6/. The unresolved parameters
should be used only for self-shielding calculation.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barn) (barn)
----------------------------------------------------------
Total 9.1626e+01
Elastic 6.5644e+00
n,gamma 8.5061e+01 2.8797e+02
n,alpha 1.5070e-06
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Sum of partial cross sections.
MT= 2 Elastic scattering cross section
Obtained by subtracting non-elastic scattering cross sections
from total cross section.
MT= 4 (n,n') cross section
Calculated with CCONE code /6/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /6/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /6/.
MT= 22 (n,na) cross section
Calculated with CCONE code /6/.
MT= 24 (n,2na) cross section
Calculated with CCONE code /6/.
MT= 28 (n,np) cross section
Calculated with CCONE code /6/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /6/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /6/.
MT=102 Capture cross section
Calculated with CCONE code /6/.
MT=103 (n,p) cross section
Calculated with CCONE code /6/.
MT=104 (n,d) cross section
Calculated with CCONE code /6/.
MT=105 (n,t) cross section
Calculated with CCONE code /6/.
MT=106 (n,He3) cross section
Calculated with CCONE code /6/.
MT=107 (n,a) cross section
Calculated with CCONE code /6/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /6/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /6/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /6/.
MT= 22 (n,na) reaction
Calculated with CCONE code /6/.
MT= 24 (n,2na) reaction
Calculated with CCONE code /6/.
MT= 28 (n,np) reaction
Calculated with CCONE code /6/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /6/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /6/.
MT=102 Capture reaction
Calculated with CCONE code /6/.
*****************************************************************
Nuclear Model Calculation with CCONE code /6/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,1,2,4,10 (see Table 1)
* optical model potential
neutron omp: Kunieda,S. et al./7/ (+)
proton omp: Koning,A.J. and Delaroche,J.P./8/
deuteron omp: Lohr,J.M. and Haeberli,W./9/
triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/
He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/
alpha omp: Huizenga,J.R. and Igo,G./11/
(+) omp parameters were modified.
2) Two-component exciton model/12/
* Global parametrization of Koning-Duijvestijn/13/
was used.
* Gamma emission channel/14/ was added to simulate direct
and semi-direct capture reaction.
3) Hauser-Feshbach statistical model
* Width fluctuation correction/15/ was applied.
* Neutron, proton, deuteron, triton, He3, alpha and gamma
decay channel were taken into account.
* Transmission coefficients of neutrons were taken from
optical model calculation.
* The level scheme of the target is shown in Table 1.
* Level density formula of constant temperature and Fermi-gas
model were used with shell energy correction/16/.
Parameters are shown in Table 2.
* Gamma-ray strength function of enhanced generalized
Lorentzian form/17/,/18/ was used for E1 transition.
For M1 and E2 transitions the standard Lorentzian form was
adopted. The prameters are shown in Table 3.
------------------------------------------------------------------
Tables
------------------------------------------------------------------
Table 1. Level Scheme of Gd-154
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 0 + *
1 0.12307 2 + *
2 0.37100 4 + *
3 0.68066 0 +
4 0.71766 6 + *
5 0.81548 2 +
6 0.99625 2 +
7 1.04758 4 +
8 1.12778 3 +
9 1.13596 2 +
10 1.14443 8 + *
11 1.18208 0 +
12 1.23310 3 -
13 1.24127 1 -
14 1.25162 3 -
15 1.26378 4 +
16 1.27699 4 +
17 1.29417 2 +
18 1.29547 0 +
19 1.36500 1 +
20 1.36587 6 +
21 1.39752 2 -
22 1.40407 5 -
23 1.41442 1 -
24 1.41814 2 +
25 1.43258 5 +
-------------------
*) Coupled levels in CC calculation
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Gd-155 20.5000 0.9639 3.7045 0.5229 -1.4800 5.7609
Gd-154 18.5215 1.9340 3.6018 0.5706 -0.6048 7.0075
Gd-153 20.9000 0.9701 3.9793 0.5231 -1.6694 5.9506
Gd-152 18.3157 1.9467 3.2774 0.5203 0.2124 5.9623
Eu-154 19.2000 0.0000 3.6717 0.5485 -2.4486 4.8922
Eu-153 17.3400 0.9701 3.8805 0.5963 -1.6297 6.1695
Eu-152 19.7700 0.0000 4.2144 0.5244 -2.4180 4.7265
Eu-151 21.0000 0.9765 3.8814 0.4854 -1.1094 5.2279
Sm-153 20.0000 0.9701 3.6781 0.5579 -1.8633 6.3072
Sm-152 19.7000 1.9467 3.6242 0.5066 -0.0488 6.1904
Sm-151 20.8000 0.9765 3.9732 0.5224 -1.6295 5.9141
Sm-150 19.2000 1.9596 3.2458 0.5078 0.1619 6.0033
Sm-149 19.2000 0.9831 2.9030 0.5042 -0.6887 4.8887
Sm-148 18.4000 1.9728 2.0339 0.5337 0.3686 5.9610
--------------------------------------------------------
Table 3. Gamma-ray strength function for Gd-155
--------------------------------------------------------
K0 = 2.000 E0 = 4.500 (MeV)
* E1: ER = 11.20 (MeV) EG = 2.60 (MeV) SIG = 180.00 (mb)
ER = 15.20 (MeV) EG = 3.60 (MeV) SIG = 242.00 (mb)
* M1: ER = 7.63 (MeV) EG = 4.00 (MeV) SIG = 1.82 (mb)
* E2: ER = 11.73 (MeV) EG = 4.25 (MeV) SIG = 3.70 (mb)
--------------------------------------------------------
References
1) Mughabghab, S.F.: "Neutron Cross Sections, Vol. I, Part B",
Academic Press (1984).
2) Macklin, R.L.: Nucl. Sci. Eng., 95. 304 (1987).
3) Leinweber, G et al.: Nucl. Sci. Eng., 154, 261 (2006).
4) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
5) Iwamoto,O.: JAERI-Data/Code 2003-020 (2003).
6) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
7) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).
8) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)
[Global potential].
9) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).
10) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.
J.H.Williams Lab., Univ. Minnesota (1969).
11) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).
12) Kalbach,C.: Phys. Rev. C33, 818 (1986).
13) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).
14) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).
15) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).
16) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151
(1994).
17) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).
18) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).