61-Pm-151 JAEA EVAL-Dec09 N.Iwamoto
DIST-MAY10 20100119
----JENDL-4.0 MATERIAL 6161
-----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 : 2.4 eV - 100.0 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 5.0747e+02
Elastic 7.0239e+00
n,gamma 5.0020e+02 1.2609e+03
n,alpha 3.2328e-10
----------------------------------------------------------
(*) 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: 0,1,4,8,12,23,35 (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-151
-------------------
No. Ex(MeV) J PI
-------------------
0 0.00000 5/2 + *
1 0.08512 7/2 + *
2 0.11679 5/2 -
3 0.17508 7/2 -
4 0.19727 9/2 + *
5 0.25569 3/2 +
6 0.26116 9/2 -
7 0.32468 5/2 +
8 0.32960 11/2 + *
9 0.34380 11/2 -
10 0.42645 1/2 +
11 0.42715 7/2 +
12 0.48670 13/2 + *
13 0.49750 13/2 -
14 0.50789 5/2 +
15 0.52434 3/2 +
16 0.53206 7/2 -
17 0.54037 3/2 -
18 0.55200 9/2 +
19 0.57740 5/2 -
20 0.59600 9/2 -
21 0.59710 15/2 -
22 0.64010 11/2 -
23 0.65760 15/2 + *
24 0.70100 11/2 +
25 0.71920 7/2 +
26 0.74655 3/2 -
27 0.75557 5/2 +
28 0.77360 3/2 -
29 0.78100 7/2 +
30 0.80946 7/2 -
31 0.82750 17/2 -
32 0.84097 3/2 +
33 0.85230 1/2 +
34 0.85299 5/2 +
35 0.85390 17/2 + *
36 0.86600 13/2 +
37 0.87058 7/2 -
38 0.87471 3/2 +
-------------------
*) 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-152 18.2003 0.0000 3.4439 0.4590 -1.0726 3.0071
Pm-151 17.4614 0.9765 3.7662 0.5765 -1.3653 5.8316
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
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
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
--------------------------------------------------------
Table 3. Gamma-ray strength function for Pm-152
--------------------------------------------------------
K0 = 2.000 E0 = 4.500 (MeV)
* E1: ER = 12.57 (MeV) EG = 3.27 (MeV) SIG = 125.54 (mb)
ER = 16.16 (MeV) EG = 5.29 (MeV) SIG = 251.08 (mb)
* M1: ER = 7.68 (MeV) EG = 4.00 (MeV) SIG = 1.26 (mb)
* E2: ER = 11.80 (MeV) EG = 4.29 (MeV) SIG = 3.40 (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).