61-Pm-149 JAEA EVAL-Dec09 N.Iwamoto
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 6155
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-12 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 resonances
No resolved resonance parameters
Unresolved resonance region : 2.7 eV - 180.0 keV
The unresolved resonance paramters (URP) were determined by
ASREP code /1/ so as to reproduce the evaluated total and
capture cross sections calculated with optical model code
CCOM /2/ and CCONE /3/. 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 1.4069e+03
Elastic 5.8201e+00
n,gamma 1.4005e+03 1.2034e+03
n,alpha 1.2883e-04
----------------------------------------------------------
(*) 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 /3/.
MT= 16 (n,2n) cross section
Calculated with CCONE code /3/.
MT= 17 (n,3n) cross section
Calculated with CCONE code /3/.
MT= 22 (n,na) cross section
Calculated with CCONE code /3/.
MT= 24 (n,2na) cross section
Calculated with CCONE code /3/.
MT= 28 (n,np) cross section
Calculated with CCONE code /3/.
MT= 32 (n,nd) cross section
Calculated with CCONE code /3/.
MT= 33 (n,nt) cross section
Calculated with CCONE code /3/.
MT= 41 (n,2np) cross section
Calculated with CCONE code /3/.
MT= 51-91 (n,n') cross section
Calculated with CCONE code /3/.
MT=102 Capture cross section
Calculated with CCONE code /3/.
MT=103 (n,p) cross section
Calculated with CCONE code /3/.
MT=104 (n,d) cross section
Calculated with CCONE code /3/.
MT=105 (n,t) cross section
Calculated with CCONE code /3/.
MT=106 (n,He3) cross section
Calculated with CCONE code /3/.
MT=107 (n,a) cross section
Calculated with CCONE code /3/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with CCONE code /3/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Calculated with CCONE code /3/.
MT= 17 (n,3n) reaction
Calculated with CCONE code /3/.
MT= 22 (n,na) reaction
Calculated with CCONE code /3/.
MT= 24 (n,2na) reaction
Calculated with CCONE code /3/.
MT= 28 (n,np) reaction
Calculated with CCONE code /3/.
MT= 32 (n,nd) reaction
Calculated with CCONE code /3/.
MT= 33 (n,nt) reaction
Calculated with CCONE code /3/.
MT= 41 (n,2np) reaction
Calculated with CCONE code /3/.
MT= 51-91 (n,n') reaction
Calculated with CCONE code /3/.
MT=102 Capture reaction
Calculated with CCONE code /3/.
*****************************************************************
Nuclear Model Calculation with CCONE code /3/
*****************************************************************
Models and parameters used in the CCONE calculation
1) Optical model
* coupled channels calculation
coupled levels: 0,6,13,32 (see Table 1)
* optical model potential
neutron omp: Kunieda,S. et al./4/ (+)
proton omp: Koning,A.J. and Delaroche,J.P./5/
deuteron omp: Lohr,J.M. and Haeberli,W./6/
triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./7/
He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./7/
alpha omp: Huizenga,J.R. and Igo,G./8/
(+) omp parameters were modified.
2) Two-component exciton model/9/
* Global parametrization of Koning-Duijvestijn/10/
was used.
* Gamma emission channel/11/ was added to simulate direct
and semi-direct capture reaction.
3) Hauser-Feshbach statistical model
* Width fluctuation correction/12/ 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/13/.
Parameters are shown in Table 2.
* Gamma-ray strength function of enhanced generalized
Lorentzian form/14/,/15/ 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 Pm-149
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 7/2 + *
1 0.11431 5/2 +
2 0.18863 3/2 +
3 0.21131 5/2 +
4 0.24021 11/2 -
5 0.27017 7/2 -
6 0.28821 9/2 + *
7 0.36005 7/2 +
8 0.38756 1/2 +
9 0.39677 5/2 +
10 0.41545 3/2 +
11 0.42528 7/2 +
12 0.46219 3/2 -
13 0.49759 11/2 + *
14 0.51008 15/2 -
15 0.51565 9/2 -
16 0.53786 5/2 -
17 0.54713 7/2 +
18 0.55200 11/2 -
19 0.55830 9/2 +
20 0.63650 1/2 +
21 0.65102 5/2 +
22 0.65484 7/2 -
23 0.66655 7/2 -
24 0.71672 3/2 -
25 0.72100 7/2 +
26 0.74458 5/2 +
27 0.75038 9/2 +
28 0.75150 3/2 +
29 0.75865 9/2 +
30 0.76819 7/2 +
31 0.77135 13/2 -
32 0.77888 13/2 + *
33 0.78672 3/2 +
34 0.79101 11/2 -
35 0.80864 11/2 +
-------------------
*) Coupled levels in CC calculation
Table 2. Level density parameters
--------------------------------------------------------
Nuclide a* Pair Eshell T E0 Ematch
1/MeV MeV MeV MeV MeV MeV
--------------------------------------------------------
Pm-150 17.9970 0.0000 4.0234 0.4210 -0.7878 2.5000
Pm-149 17.2625 0.9831 3.6138 0.5926 -1.4731 6.0264
Pm-148 18.3000 0.0000 2.8623 0.4670 -1.0648 3.0412
Pm-147 17.0632 0.9897 2.3331 0.6101 -1.2455 5.9682
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
Nd-146 18.1900 1.9863 1.6792 0.5692 0.1138 6.4542
Nd-145 18.5400 0.9965 1.1101 0.5235 -0.2928 4.6189
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
Pr-146 17.5893 0.0000 2.4188 0.5462 -1.6453 4.0472
Pr-145 16.8637 0.9965 1.7883 0.6002 -0.8883 5.5766
Pr-144 15.5000 0.0000 0.9153 0.6715 -1.9662 5.0412
Pr-143 16.6639 1.0035 0.4682 0.6161 -0.5920 5.4208
--------------------------------------------------------
Table 3. Gamma-ray strength function for Pm-150
--------------------------------------------------------
K0 = 2.000 E0 = 4.500 (MeV)
* E1: ER = 12.88 (MeV) EG = 3.43 (MeV) SIG = 123.69 (mb)
ER = 16.00 (MeV) EG = 5.18 (MeV) SIG = 247.38 (mb)
* M1: ER = 7.72 (MeV) EG = 4.00 (MeV) SIG = 1.24 (mb)
* E2: ER = 11.86 (MeV) EG = 4.31 (MeV) SIG = 3.43 (mb)
--------------------------------------------------------
References
1) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)
[in Japanese].
2) Iwamoto,O.: JAERI-Data/Code 2003-020 (2003).
3) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).
4) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).
5) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)
[Global potential].
6) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).
7) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.
J.H.Williams Lab., Univ. Minnesota (1969).
8) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).
9) Kalbach,C.: Phys. Rev. C33, 818 (1986).
10) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).
11) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).
12) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).
13) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151
(1994).
14) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).
15) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).