60-Nd-150 JAEA+ EVAL-Dec09 N.Iwamoto,A.Zukeran,K.Shibata
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 6049
-----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 13.69 keV
Neutron widths were adopted from Tellier/1/. Radiation
widths were taken from the recommendation by Mughabghab and
garber/2/. The average radiation width of 0.070 eV was
assumed for levels which had no measured radiation width.
A negative resonance was added so as to reproduce the
capture cross section of 1.2+-0.2 barns at 0.0253 eV /3/.
In JENDL-4, the data for 78.92 - 486.4 eV were replaced with
the ones obtained by Barry et al./4/ The parameters for
the negative resonance were re-adjusted.
Unresolved resonance region : 13.69 keV - 300.0 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /5/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
OPTMAN /6/ and CCONE /7/. 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 5.8344e+00
Elastic 4.7938e+00
n,gamma 1.0406e+00 1.4163e+01
n,alpha 8.6016e-17
----------------------------------------------------------
(*) 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 /7/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /7/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /7/.
MT= 22 (n,na) cross section
Calculated with CCONE code /7/.
MT= 24 (n,2na) cross section
Calculated with CCONE code /7/.
MT= 28 (n,np) cross section
Calculated with CCONE code /7/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /7/.
MT= 33 (n,nt) cross section
Calculated with CCONE code /7/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /7/.
MT=102 Capture cross section
Calculated with CCONE code /7/.
MT=103 (n,p) cross section
Calculated with CCONE code /7/.
MT=104 (n,d) cross section
Calculated with CCONE code /7/.
MT=105 (n,t) cross section
Calculated with CCONE code /7/.
MT=106 (n,He3) cross section
Calculated with CCONE code /7/.
MT=107 (n,a) cross section
Calculated with CCONE code /7/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /7/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /7/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /7/.
MT= 22 (n,na) reaction
Calculated with CCONE code /7/.
MT= 24 (n,2na) reaction
Calculated with CCONE code /7/.
MT= 28 (n,np) reaction
Calculated with CCONE code /7/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /7/.
MT= 33 (n,nt) reaction
Calculated with CCONE code /7/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /7/.
MT=102 Capture reaction
Calculated with CCONE code /7/.
*****************************************************************
Nuclear Model Calculation with CCONE code /7/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,1,2,4,7,10 (see Table 1)
* optical model potential
neutron omp: Kunieda,S. et al./8/ (+)
proton omp: Koning,A.J. and Delaroche,J.P./9/
deuteron omp: Lohr,J.M. and Haeberli,W./10/
triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/
He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/
alpha omp: McFadden,L. and Satchler,G.R./12/
(+) omp parameters were modified.
2) Two-component exciton model/13/
* Global parametrization of Koning-Duijvestijn/14/
was used.
* Gamma emission channel/15/ was added to simulate direct
and semi-direct capture reaction.
3) Hauser-Feshbach statistical model
* Width fluctuation correction/16/ 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/17/.
Parameters are shown in Table 2.
* Gamma-ray strength function of enhanced generalized
Lorentzian form/18/,/19/ 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 Nd-150
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 0 + *
1 0.13021 2 + *
2 0.38145 4 + *
3 0.67537 0 +
4 0.72040 6 + *
5 0.85066 2 +
6 0.85294 1 -
7 0.93486 3 - *
8 1.06195 2 +
9 1.12900 5 -
10 1.12970 8 + *
11 1.13780 4 +
12 1.18231 0 +
13 1.20063 3 +
14 1.25000 0 +
15 1.28391 1 -
16 1.30750 0 +
17 1.31800 1 -
-------------------
*) Coupled levels in CC calculation
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Nd-151 19.8000 0.9765 3.4048 0.5128 -1.0731 5.3158
Nd-150 20.0000 1.9596 3.4363 0.5263 -0.3405 6.6204
Nd-149 20.9000 0.9831 3.5199 0.4992 -1.1865 5.3955
Nd-148 21.1000 1.9728 2.8636 0.4784 0.2048 5.9010
Nd-147 19.7000 0.9897 2.4886 0.4934 -0.5694 4.7470
Pr-150 17.9970 0.0000 3.3122 0.4633 -1.0542 3.0000
Pr-149 17.2625 0.9831 3.6354 0.5953 -1.5169 6.0817
Pr-148 15.5000 0.0000 3.2403 0.6014 -1.8696 4.4395
Pr-147 17.0632 0.9897 3.0053 0.5856 -1.1357 5.6888
Ce-149 18.6229 0.9831 3.3637 0.3046 0.9683 1.9831
Ce-148 17.9032 1.9728 3.0589 0.5775 -0.3257 6.8383
Ce-147 18.4207 0.9897 2.8111 0.5589 -1.1482 5.6286
Ce-146 17.6964 1.9863 2.1733 0.5745 0.0448 6.5077
Ce-145 18.2180 0.9965 1.7406 0.5686 -0.8969 5.4793
Ce-144 17.4894 2.0000 1.0129 0.5822 0.3675 6.2813
--------------------------------------------------------
Table 3. Gamma-ray strength function for Nd-151
--------------------------------------------------------
K0 = 1.800 E0 = 4.500 (MeV)
* E1: ER = 12.66 (MeV) EG = 3.31 (MeV) SIG = 123.94 (mb)
ER = 16.13 (MeV) EG = 5.27 (MeV) SIG = 247.88 (mb)
* M1: ER = 7.70 (MeV) EG = 4.00 (MeV) SIG = 1.14 (mb)
* E2: ER = 11.83 (MeV) EG = 4.30 (MeV) SIG = 3.30 (mb)
--------------------------------------------------------
References
1) Tellier, H.: CEA-N-1459 (1971).
2) Mughabghab, S.F. and Garber, D.I.: "Neutron Cross Sections,
Vol.1, Resonance Parameters", BNL 325, 3rd ed., Vol. 1,
(1973).
3) Fedorova, A.F., et al.: "Proc. 3rd All-union Conf. on Neutron
Physics, Kiev 1975", Vol. 1, 169.
4) Barry, D.P., et al.: Nucl. Sci. Eng., 153, 8 (2006).
5) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
6) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).
7) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
8) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).
9) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)
[Global potential].
10) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).
11) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.
J.H.Williams Lab., Univ. Minnesota (1969).
12) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966).
13) Kalbach,C.: Phys. Rev. C33, 818 (1986).
14) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).
15) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).
16) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).
17) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151
(1994).
18) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).
19) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).