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Entry No. D1377

N.Shinohara1, S.Usuda1, S.Ichikawa1, T.Suzuki1, M.Magara1, H.Okashita1, H.Yoshikawa2, T.Horiguchi3, Y.Iwata3, S.Shibata4, I.Fujiwara5
Japan Atomic Research Institute (JAERI1
Tokyo Metropolitan Univ., Hachioji, Tokyo2
Hiroshima Univ., Hiroshima and Higashi-Hiroshima3
Institute for Nuclear Study, Univ. of Tokyo, Tanashi4
Kyoto Univ.5
Physical Review, Part C, Nuclear Physics34(1986)909

Actinides produced by 12C+242Pu and 16O+238U reactions

Click on the data number to see the plot. Or select the box to plot multiple data.
DataFilePhysical quantitiesReaction(s)Energies
1 *INC-ENGY-LAB SIGMA
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 242PU(12C,4*N)250FM; between 6.512E+01 and 8.431E+01 MEV
2 *INC-ENGY-LAB SIGMA8)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 242PU(12C,X)246CF; between 6.502E+01 and 9.327E+01 MEV
3 *INC-ENGY-LAB SIGMA9)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 242PU(12C,X)245CF; between 7.586E+01 and 9.327E+01 MEV
4 *INC-ENGY-LAB SIGMA10)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 242PU(12C,X)244CF; between 8.431E+01 and 8.788E+01 MEV
5 *INC-ENGY-LAB SIGMA
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 238U(16O,4*N)250FM; between 8.481E+01 and 1.009E+02 MEV
6 *INC-ENGY-LAB SIGMA11)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 238U(16O,X)246CF; between 8.475E+01 and 1.229E+02 MEV
7 *INC-ENGY-LAB SIGMA12)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 238U(16O,X)245CF; between 9.476E+01 and 1.149E+02 MEV
8 *INC-ENGY-LAB SIGMA13)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 238U(16O,X)244CF; between 1.008E+02 and 1.048E+02 MEV
9 *INC-ENGY-LAB SIGMA14)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 242PU(12C,X)242CM; between 6.474E+01 and 9.331E+01 MEV
10 *INC-ENGY-LAB SIGMA15)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 (242PU(12C,X)243CM+242PU(12C,X)244CM); between 6.738E+01 and 9.333E+01 MEV
11 *INC-ENGY-LAB SIGMA16)
INC-ENGY-LAB: Incident energy in lab. system #3; SIGMA: Total cross section #1		 238U(16O,X)242CM; between 8.495E+01 and 1.236E+02 MEV

8) Independent cross section
9) Independent cross section
10) Independent cross section
11) Independent cross section
12) Independent cross section
13) Independent cross section
14) Cumulative cross section
15) Independent cross section
16) Independent cross section
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