25-Mn- 55
25-Mn- 55 JAERI,MAPI EVAL-MAR87 K.Shibata,T.Hojuyama
NST 26, 955 (1989) DIST-MAY10 20100121
----JENDL-4.0 MATERIAL 2525
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 Resonance parameters were evaluated by T.Hojuyama (mapi).
Multistep Hauser-Feshbach calculations were performed
by K.Shibata (jaeri).
88-01 Compiled by K.Shibata (jaeri).
88-03 Covariance data added
91-08 Modifed by B.Yu (ciae) and S.Chiba (ndc/jaeri) as follows
for JENDL fusion file/20/.
Compiled by B.Yu.
Cross sections were mainly taken from JENDL-3.1. The (n,n')
continumm cross section (mt=91) in the whole energy region and
its spectra were taken from the sincros-II /21/ calculation.
Several discrete level scattering cross sections (mt=67, 68, 69,
70, 71, 72, 73, 74, 75, 76, 77, 78, 79) and their angular distri-
butions were deleted as well as their covariance matrices
because they are included in the new continuum inelastic
scattering cross section taken from the sincros-II calculation.
93-08 JENDL-3.2
File-6 of the JENDL fusion file was converted to files 4
and 5.
Data were compiled by K. Shibata (jaeri).
02-01 Compiled by K.Shibata for JENDL-3.3.
***** Modified parts for JENDL-3.3 ****************************
(1,451) Updated
(3,3) Deleted
(3,203-207) Calcualted
(3,251) Deleted
(4,2) Transformation matrix deleted
(4,16),(4,22), Deleted
(4,28),(4,91) Deleted
(5,16-91) Deleted
(6,16-91) Taken from JENDL fusion file
(6,203-207) Taken from JENDL fusion file
(12,102) Modified
(15,102) Experimental data were inserted for
En = 14-559 keV.
(33,2) Taken from JENDL-3.2 covariance file.
****************************************************************
10-01 Compiled by K.Shibata for JENDL-4.0.
***** Modified parts for JENDL-4.0 ****************************
(1,451) Updated
(2,151) Evaluated by Derrien et al.
(3,1),(3,2) Re-calculated
(3,102) Background evaluated by Derrien et al.
(32,151) Evaluated by Derrien et al.
****************************************************************
The details of the resolved resonance parameters are given below:
==================================================================
EVALUATION of the RESONANCE PARAMETERS of Mn-55 in the ENERGY
RANGE 0 to 122 keV- H. Derrien, L.C. Leal, N.M.Larson, D. Wiarda
K. Guber, and G. Arbanas.
The resonance parameters were obtained from a sequential Bayes
SAMMY analysis of the most recent experimental neutron
transmissions and capture cross sections in the resolved energy
range: Harvey et al. transmissions measured at ORELA in 1980,
Aerts et al. Capture cross sections measured at GELINA in 2006,
and Guber et al. Capture cross section measured at ORELA in 2007.
For the evaluation in the thermal energy range Widder et al.
(1975) capture cross section, Cote et al. (1964) total cross
sections, and Rainwater et al. (1964) total cross sections were
considered. The thermal capture cross sections were normalized at
the 0.0253 eV value of 13.27 b which is an average of the
available experimental values, consistent with the recent
evaluation of Trkov et al.(2007). The thermal cross sections
calculated by the resonance parameters are the following:
Res. Int.
Capture 13.274 b 13.514
Total 15.390 b -
Scattering 2.116 b -
The capture resonance integral is 13.516 b in the energy range
0.5 eV to 120 keV.
Most of the p-wave resonances are not observed in the experimental
transmission data. For those resonances only the capture area
could be obtained with good accuracy. The capture area is
proportional to gamman*gammag / gammatot and only the product
gamman*gammag could be defined. A solution is to assign to all
this resonances a constant capture width value equal to an
estimated averaged value. In this case the SAMMY fit to the
capture data is generally poor. The solution of varying both the
capture width and the neutron width in the SAMMY fit has been
chosen is the evaluation. The resulting capture widths do not
deviate too much from an average value. The fit is obviously not
unique but give a good description of the experimental data. The
study of the statistical properties of the neutron widths has
shown that the obtained set of parameters is reasonable.
Only s-wave and p-wave resonances are given in the evaluation.
However the study of the statistical properties of the p-wave
resonance parameters has shown that 25% of them(the very small
one) could be d-wave resonances. Including these possible d-wave
resonances in the p-wave resonances has a negligible effect on
the calculated capture cross section.
Two components of the capture cross section are given in the
evaluation: the first component is calculated by the observed
resonance parameters; the second component is given as a File 3
background. This background stands for the contribution of the
the contribution of the direct capture, for the contribution of
non observed d-wave resonances, and for possible errors in the
errors in the calculation of the multiple scattering effect by
SAMMY in the experimental capture cross sections. The estimation
of the average d-wave contribution below 122 keV was obtained from
SAMMY/URR. The error on the background file is important (20% to
30%), contributing to the most part of the uncertainty on the
average captur cross section
The following Table compares the average capture cross section to
the experimental values of Lerigoleur , and of Garg and Macklin.
The present evaluation is systematically lower than Lerigoleur
(absolute measurement) by 12% on average; part of the discrepancy
could be due to the inaccuracy of the calculation of the d-wave
component in the background file.
___________________________________________________________
Energy Range Present Results Lerigoleur Garg-Macklin
keV mb mb Mb
___________________________________________________________
15 - 20 47.98+/-2.05 57.05+/-4.56 48.6
20 - 30 35.79+/-1.79 40.97+/-3.28 44.6
30 - 40 25.24+/-1.20 27.43+/-2.19 44.7
40 - 50 25.24+/-1.20 19.58+/-1.57 28.2
50 - 60 20.40+/-1.20 20.41+/-1.63 26.0
60 - 80 16.69+/-1.30 20.19+/-1.61 21.5
80 -100 15.00+/-1.10 17.65+/-1.41 16.3
100 -120 11.63+/-1.10 12.65+/-1.41 14.3
___________________________________________________________
Resonance parameter covariance was generated in the resolved
energy region (1.0-5 eV to 125 keV) with the computer code SAMMY
at ORNL. Experimental data and uncertainties were used to generate
covariance data. SAMMY covariance information was converted in
the ENDF FILE32 representation. The covariance information was
processed with the PUFF-IV code.
The details of the evaluation are in progress of publication in
an ORNL/TM report.
References:
HA 90 Harvey, private communication, 2007
AE 06, private communication 2006
GU 07 Guber, to be published, 2007
WI 75, Wilder, R_EIR-217, 1975
CO 64, Cote, PR/B, 134, 1047, 1964
RA 64, Rainwater, RSI, 35, 263, 1964
TR 07, private communication 2007
LE 76, Lerigoleur CEA-R-4888, 1976
GA 78, Garg-Macklin, PR/C, 18, 2079, 1978
==================================================================
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 Resonance parameters
mt=151 Resolved resonance parameters for MLBW formula
The parameters of the lowest four resonances were taken
from the work of Macklin /1/. Others were taken from the
compilation of Mughabghab et al./2/ except that the
parameters of two negative resonances were adjusted so as
to fit to experimental thermal cross sections.
Resonance region : 1.0e-5 eV to 100 keV.
Scattering radius: 5.15 fm
Calculated 2200-m/s cross sections and res. integrals
2200-m/s res. integ.
elastic 2.167 b -
capture 13.413 b 11.77 b
total 15.579 b -
***** JENDL-4.0 ****************************************
The resolved resonance parameters were taken from the work
done by Derrien et al. See above.
The unresolved resonance parameters were obtained so as to
reproduce the total and capture cross sections in the
energy region from 125 keV to 1 MeV. The unresolved
parameters should be used only for self-shielding
calculations.
**********************************************************
mf=3 Neutron cross sections
mt=1 Total
Below 100 keV : No background
Above 100 keV : Based on the experimental data /3,4,5/.
***** JENDL-4.0 ****************************************
Below 125 keV : Background due to capture
Above 125 keV : Based on the experimental data /3,4,5/.
**********************************************************
mt=2 Elastic scattering
(total) - (nonelastic cross section)
mt=4,51-66,91 Inelastic scattering
Statistical-model calculations were performed using the
tng code /6/. The precompound process was considered
above 5 MeV. The calculated cross section of mt=51
was multiplied by a factor of 1.2.
For the levels of mt=51,52,57,61,64,65,67,70,
the direct process components were taken into account
by the DWBA calculations.
The optical potential parameters used are as follows/7/
(in the units of MeV and fm):
V = 49.747 - 0.4295*E - 0.0003*E**2 r0 = 1.287 a0 = 0.56
Ws = 11.2 - 0.09*E rs = 1.345 as = 0.47
Vso= 6.2 rso= 1.120 aso = 0.47
The level scheme was taken from ref./8/.
no. energy(MeV) spin-parity
g.s. 0.0 5/2 -
1. 0.126 7/2 -
2. 0.984 9/2 -
3. 1.290 1/2 -
4. 1.292 11/2 -
5. 1.293 1/2 -
6. 1.528 3/2 -
7. 1.884 7/2 -
8. 2.015 7/2 -
9. 2.198 7/2 -
10. 2.215 5/2 -
11. 2.252 3/2 -
12. 2.267 5/2 -
13. 2.312 13/2 -
14. 2.366 5/2 -
15. 2.398 9/2 +
16. 2.427 1/2 +
17. 2.563 3/2 -
18. 2.727 7/2 -
19. 2.753 5/2 -
20. 2.822 9/2 -
21. 2.824 5/2 -
22. 2.873 1/2 -
23. 2.954 3/2 -
24. 2.976 3/2 -
25. 2.992 7/2 -
26. 3.006 3/2 -
27. 3.036 11/2 -
28. 3.038 1/2 -
29. 3.040 3/2 +
Levels above 3.046 MeV were assumed to be overlapping.
***** JENDL-3.2 ****************************************
The cross sections for mt=67-79 were deleted and that for
mt=91 was modified so that the calculated spectra could
give a better fit to the measured ddx data.
*********************************************************
mt=16,22,28,103,107 (n,2n),(n,n'a),(n,n'p),(n,p) and (n,a)
cross sections
Calculated with tng.
Global optical-potential parameters were employed
for protons and alpha-particles /9,10/.
mt=102 Radiative capture cross section
Below 100 keV : Resonance parameters given (no background)
Above 100 keV : Based on the experimental data /11/-/15/.
***** JENDL-4.0 ****************************************
Below 125 keV : Background evaluated by Derrien et al.
Above 125 keV : Based on the experimental data /11/-/15/.
**********************************************************
mt=104 (n,d) cross section
The excitation function of the (n,p) cross section
calculated with tng was used for the (n,d) reaction by
shifting the threshold energy. The cross sections were
normalized to the experimental datum at 14.1 MeV /16/.
mt=105 (n,t) cross section
The excitation function of the (n,p) cross section
calculated with tng was used for the (n,t) reaction by
shifting the threshold energy. The cross sections were
normalized to the experimental datum at 14.7 MeV /17/.
mt=106 (n,He-3) cross section
Based on the experimental data /18,19/.
mt=203 : Total proton production
Sum of mt=28 and 103.
mt=204 : Total deuteron production
Equal to mt=104.
mt=205 : Total triton production
Equal to mt=105.
mt=206 : Total He-3 production
Equal to mt=106.
mt=207 : Total alpha production
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2,51-66
Optical and statistical-model calculations
the components of the direct process were added to
the levels of mt=51,52,57,61,64,65 by the DWBA
calculations.
mf=6 Energy-angle distributions of secondary particles
mt=16, 22, 28, 91, 203, 204, 205, 206, 207
Taken from the file-6 of the JENDL fusion file.
mf=12 Photon production multiplicities
mt=4,16,22,28,102,103,107
Calculated with tng.
For mt=102, modified by using gamma-ray intensity data
in ENSDF below thermal energy.
****** JENDL-3.3 ************************************
For mt=102, multiplicities were modified between 1.0e-5
and 5.59e+5 eV.
******************************************************
mf=14 Photon angular distributions
mt=4,16,22,28,102,103,107
Assumed to be isotropic.
mf=15 Photon energy distributions
mt=4,16,22,28,102,103,107
Calculated with tng.
For mt=102, modified by using gamma-ray intensity data
in ENSDF below thermal energy.
****** JENDL-3.3 ************************************
For mt=2, experimental data /22/ were inserted between
14 and 559 keV.
******************************************************
mf=32 Covariances of resolved resonance parameters
mt=151
Based on experimental data. /23/
****** JENDL-4.0 *************************************
Evalauted by Derrien et al.
*******************************************************
mf=33 Covariance data
mt=1,2,4,16,22,28,51-66,91,102,103,104,105,106,107
Estimated from experimental data.
Refernces
1) Macklin, R.L.: Nucl. Sci. Eng., 89, 362 (1985).
2) Mugabghab, S.F., Divadeenam, M. and Holden, N.E.: "Neutron
Cross Sections", Vol. 1, Part A, Academic Press (1981).
3) Cierjacks, S., Forti, P., Kopsch, D., Kropp, L., Nebe, J.
and Unseld, H.: "High Resolution Total Cross Sections
for Na, Cl, K, V, Mn and Co between 0.5 and 30 MeV",
KfK-1000 (1968).
4) Pineo, W.F.E., Divadeenam, M., Bilpuch, E.G., Seth, K.K.
and Newson, H.W.: Ann. Phys., 84, 165 (1974).
5) Garg, J.B., Rainwater, J. and Havens, Jr., W.W.:
Nucl. Sci. Eng., 65, 76 (1978).
6) Fu, C.Y.: "A Consistent Nuclear Model for Compound and
Precompound Reactions with Conservation of Angular
Momentum", ORNL/TM-7042 (1980).
7) Fu, C.Y.: Private communication (1985).
8) Zhou Enchen, Huo Junde, Zhou Chunmei, Lu Xiane and
Wang Lizheng: Nucl. Data Sheets, 44, 463 (1985).
9) Perey, F.G.: Phys. Rev., 131, 745 (1963).
10) Huizenga, J.R. and Igo, G.J.: Nucl. Phys., 29, 462 (1962).
11) Garg, J.B., Macklin, R.L. and Halperin, J.: Phys. Rev.,
C18, 2079 (1978).
12) Dovbenko, A.G., Kolesov, V.E., Koroleva, V.P., Tolstikov,
V.A.: Atom. Energ., 26, 67 (1969).
13) Menlove, H.O., Coop, K.L., Grench, H.A. and Sher, R.:
Phys. Rev., 163, 1299 (1967).
14) Schwerer, O., Winkler-Rohatsch, M., Warhanek, H. and
Winkler, G.: Nucl. Phys., A264, 105 (1976).
15) Budnar, M., Cvelbar, F., Hodgson, E., Hudoklin, A.,
Ivkovic, V., Likar, A., Mihailovic, M.V., Martincic, R.,
Najzer, M., Perdan, A., Potokar, M. and Ramsak, V.:
"Prompt Gamma-ray Spectra and Integarted Cross Sections
for the Radiative Capture of 14 MeV Neutrons for 28
Natural Targets in the Mass Region from 12 to 208",
INDC(YUG)-6 (1979).
16) Colli, L., Iori, I., Micheletti, S. and Pignanelli, M.:
Nuovo. Cim., 21, 966 (1962).
17) Sudar, S. and Csikai, J.: Nucl. Phys., A319, 157 (1979).
18) Diksic, M., Strohal, P. and Slaus, I.: J. Inorg. Nucl.
Chem., 36, 477 (1974).
19) Wu, C.H., Woelfle, R. and Qaim, S.M.: Nucl. Phys., A329,
63 (1979).
20) Chiba, S et al.: JAERI-M 92-027, p. 35 (1992)
21) Yamamuro, N.: JAERI-M 90-006 (1990)
22) Igashira, M.: Private communication (2000).
23) Shibata, K. et al.: JAERI-Research 98-045 (1998).