27-Co- 59 KHI EVAL-AUG88 T.WATANABE
DIST-MAY10 20100115
----JENDL-4.0 MATERIAL 2725
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-08 Newly evaluated by T.Watanabe
(Kawasaki Heavy Industries, Ltd.)
94-04 JENDL-3.2.
Gamma prodction data evaluated by T.Asami (data eng.)
Other data were mainly adopted from JENDL fusion file.
Compiled by T.Nakagawa
94-05 JENDL fusion file /1/
95-02 Gamma-ray production data were taken from JENDL-3.2.
96-10 Ddx's of charged particles were corrected.
Comments modified by S. Chiba
01-08 JENDL-3.3 modified and compiled by T.Watanabe.
02-01 Covariances were estimated by T.Watanabe.
***** modified parts of JENDL-3.3 from previous version ****
(2,151) New evaluation R-M formulas
(3,1) New evaluation
(3,2) Re-calcualted
(3,203-207) Calculated
(3,251) Deleted.
(3,16) Adopted from JENDL activation file
(3,102) En>1.5MeV d/sd capture was taken into account
(4,2) Transformation matrix deleted.
(4,16-91) Deleted
(5,16-91) Deleted
(6,16-91) Taken from JENDL fusion file
(12,102) New evaluation
(15,102) New evaluation
***************************************************************
******* modified parts for JENDL-ff *************************
(3,4), (3,51-70), (4,16-70)
(3,102)
(3,2) to compensate the above cross section changes
Gamma-ray production data: new evaluation
***************************************************************
-------------------------------------------------------------
JENDL fusion file /1/ (as of Nov. 1993)
Evaluated by B.Yu (ciae) and S.Chiba (ndc/jaeri)
Compiled by B.Yu .
Cross sections were mainly taken from JENDL-3.1 except
for the (n,n') (mt=51 to 91) reactions which were taken from
new calculation with sincros-ii/2/. Energy distributions
for mt=16, 22, 28 and 91 were replaced by the sincros-ii
calculation. Ddx (mf=6) were created with f15tob program
/1/ in which modified Kumabe's systematics /3/ was used
for outgoing neutrons. Ddx of p, d and alpha were
newly created with mt=203, 204 and 207.
The ratio of precompound to compound was taken from the
sincros-ii calculation. Optical-model, level density and
other parameters used in the sincros-ii calculation are
described in ref./2/. Level schemes were determined on the
basis of ENSDF/4/.
-------------------------------------------------------------
JENDL fusion file (feb. 1995)
Capture cross section and photon production data were
taken from JENDL-3.2.
10-01 For JENDL-4.0, the total cross section was recalcualted from
partial cross sections.
***** Modified parts for JENDL-4.0 *************************
(1,451) Revised. A Japanese character was removed.
(3,1) Re-calculated
************************************************************
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2
mt=151 Resonance parameters : 1.0e-5 eV - 100 keV
Resolved resonances for Reich-Moore formula:
Parameters were evaluated based on experimental data
/5,6,7,9/ and modified to reproduce experimental total
cross sections. Negative energy levels were added to
reproduce 2200 m/s total and capture cross sections.
calculated 2200 m/s cross sections and resonance integrals
2200 m/sec res. integ.
elastic 6.02 b -
capture 37.20 b 75.8 b
total 43.22 b -
mf=3 Neutron cross sections : above 100 keV
mt=1 Total
Up to 5 MeV, based on experimental data /8,9,11/.
Above 5 MeV, total cross section was averaged values of
ref.9 and 11.
mt=2 Elastc scattering
total cross section - sum of partial cross sections
mt= 4, 51 - 70, 91 Inelastic scattering
Calculated for JENDL fusion file. The level scheme was taken
from ref./4/ contributions of the direct process was
calculated for the levels marked with '*'.
no. energy(MeV) spin-parity (direct process)
g.s 0.0 7/2-
1 1.0993 3/2- *
2 1.1905 9/2- *
3 1.2920 3/2- *
4 1.4343 1/2-
5 1.4595 11/2- *
6 1.4820 5/2- *
7 1.7450 7/2- *
8 2.0630 5/2- *
9 2.0880 7/2- *
10 2.1460 7/2-
11 2.1533 15/2-
12 2.183 5/2-
13 2.205 5/2- *
14 2.3971 9/2-
15 2.479 7/2-
16 2.537 9/2-
17 2.5405 3/2-
18 2.5816 9/2+
19 2.584 5/2-
20 4.0 5/2- *
Levels above 2.584 MeV were assumed to be overlapping.
mt=16 (n,2n)
Based on experimental data /12,13,14,15/ and Yamamuro's
theoretical calculations /16/. Modified slightly to reproduce
acitivation exp. at FNS. Same as JENDL activation file.
mt=22,28,104 (n,n alpha),(n,np),(n,d)
Yamamuro's evaluation was adopted /16/.
mt=102 capture
Statistical model calculation with casthy code /10/ was
performed. Above 1.5 MeV, semidirect capture cross section
was calculated with gnash-95/27/ and added.
The spherical optical potential parameters were evaluated to
reproduce experimental total cross sections /8,11/.
V = 49.65 - 0.114*En MeV r0= 1.241 fm a0= 0.533 fm
Ws= 8.625-0.05306*En MeV rs= 1.421 fm b = 0.292 fm
Vso= 7.724 MeV rso=1.151 fm aso=0.7 fm
mt=103 (n,p)
Based on experimental data /12,20,21,22/.
mt=107 (n,alpha)
JENDL-2 data were adopted with slight modification based on
evain's evaluation /23/ and experimental data /12,24/.
mt=203 Total proton production
sum of mt=28 and 103.
mt=204 Total deuteron production
Equal to mt=104.
mt=207 Total alpha production
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2
Optical model calculation.
mt=51-70
Calculated for JENDL fusion file with dwba and
statistical model.
mf=6 Energy-angle distributions of secondary particles
mt=16,22,28,91
Based on modified Kumabe's systematics/1/.
mt=203,204,207
Based on Kalbach's systematics/25/.
mf=12 Gamma-ray production mutiplicities and transition
probabilities
mt=16,22,28,91,103,104,107
Multiplicities were calculated with gnash /26/
mt=51-68
Transition probabilities were given.
mt=102
From energy balance.
mf=14 Gamma-ray angular distributions
mt=16,22,28,51-68,91,102,103,104,107
Isotropic distributions were assumed.
mf=15 Gamma-ray energy distributions
mt=16,22,28,91,103,104,107
Calculated with gnash /26/
mt=102
Calculated with casthy /10/ at thermal energy and with gnash
above 100 keV.
Above 1.5 MeV, semidirect capture cross section was calculated
with gnash-95/27/ and added.
Experiemental data /31/ were inserted at 22.5, 54.5 and 550
keV.
mf=33 Covariances of cross sections
mt=1, 2, 16, 102, 103, 107
Based on experimental data.
References
1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).
2) Yamamuro, N.: JAERI-M 90-006 (1990).
3) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).
4) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.
5) Garg J.B. et al.: Nucl. Sci. Eng. 65,76 (1978).
6) Spencer R.R. and Macklin, R.L.: Nucl.Sci.Eng. 61,346 (1976).
7) Mughabghab S.F. et al.:"Neutron Cross Sections Vol.1 Part A",
Academic Press (1981).
8) Foster,Jr. D.G. and Glasgow D.W.: Phys. Rev. C3, 576 (1973).
9) De Saussure, G. et al.: Annals of Nuclear Energy Vol.19,
pp.393(1992).
10) Igarasi S. and Fukahori T.: JAERI 1321 (1991).
11) Cierjacks S.: kfk-1000 (1969).
12) Ikeda Y. et al.: JAERI 1312 (1988).
13) Hasan S.J. et al.: Proc. Int. Conf. Nuclear Data for Basic
and Applied Science, Santa Fe, 1985, p.155 (1986).
14) Huang Jian-Zhou et al.: Chinese Nucl. Phys. 3,59 (1981).
15) Veeser L.R. et al.: Phys. Rev. C16, 1792 (1977).
16) Yamamuro N.: Private communication.
17) Paulsen A.: Z. Phys. 205, 226 (1967).
18) Rigaud F. et al.: Nucl. Phys. A273, 551 (1971).
19) Budnar M. et al.: INDC(YUG)-6 (1979).
20) Smith D.L. et al.: Nucl. Sci. Eng. 58, 314 (1975).
21) Williams J.R. and Alford, W.L.: Proc. Int. Conf. Nuclear Data
for Basic and Applied Science, Santa Fe, 1985, p.215 (1986).
22) Hasan S.J. et al.: J. Phys. G12, 397 (1986).
23) Evain B.P. et al.: ANL/NDM-89 (1985).
24) Meadows J.W. et al.: Ann. Nucl. Energy 14, 603 (1987).
25) Kalbach C. : Phys. Rev. C37, 2350(1988).
26) Young P.G. and Arthur E.D.: LA-6974 (1977).
29) Young P.G. et al.:FLA-12343-MS(1992).
30) Poenitz W.P.: BNL-NCS-51363(1981).
31) Igashira M.: Private communication (1999).