Abstract
Making use of a standard neutron spectrum field with a pure Maxwellian distribution, the thermal neutron cross section for the {sup 241}Am(n,f) reaction has been measured relative to the reference value of 586.2b for the {sup 235U}(n,f) reaction. For the present measurement, electrodeposited layers of {sup 241}Am and {sup 235}U have been employed as back-to-back type double fission chambers. The present result at neutron energy of 0.0253 eV is 3.15 {+-} 0.097b. The ENDF/B-VI data is in good agreement with the present value, while the JENDL-3.2 data is lower by 4.2%. The evaluated data in JEF-2.2 and by Mughabghab are higher by 0.9% and 1.6%, respectively than the present result. The ratios of the earlier experimental data to the present value are distributed between 0.89 and 1.02. (author)
Kobayashi, Katsuhei;
Yamamoto, Shuji;
Fujita, Yoshiaki;
[1]
Miyoshi, Mitsuharu;
Kimura, Itsuro;
Kanno, Ikuo;
Shinohara, Nobuo
- Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.
Citation Formats
Kobayashi, Katsuhei, Yamamoto, Shuji, Fujita, Yoshiaki, Miyoshi, Mitsuharu, Kimura, Itsuro, Kanno, Ikuo, and Shinohara, Nobuo.
Measurement of thermal neutron cross section for {sup 241}Am(n,f) reaction.
Japan: N. p.,
1997.
Web.
Kobayashi, Katsuhei, Yamamoto, Shuji, Fujita, Yoshiaki, Miyoshi, Mitsuharu, Kimura, Itsuro, Kanno, Ikuo, & Shinohara, Nobuo.
Measurement of thermal neutron cross section for {sup 241}Am(n,f) reaction.
Japan.
Kobayashi, Katsuhei, Yamamoto, Shuji, Fujita, Yoshiaki, Miyoshi, Mitsuharu, Kimura, Itsuro, Kanno, Ikuo, and Shinohara, Nobuo.
1997.
"Measurement of thermal neutron cross section for {sup 241}Am(n,f) reaction."
Japan.
@misc{etde_530403,
title = {Measurement of thermal neutron cross section for {sup 241}Am(n,f) reaction}
author = {Kobayashi, Katsuhei, Yamamoto, Shuji, Fujita, Yoshiaki, Miyoshi, Mitsuharu, Kimura, Itsuro, Kanno, Ikuo, and Shinohara, Nobuo}
abstractNote = {Making use of a standard neutron spectrum field with a pure Maxwellian distribution, the thermal neutron cross section for the {sup 241}Am(n,f) reaction has been measured relative to the reference value of 586.2b for the {sup 235U}(n,f) reaction. For the present measurement, electrodeposited layers of {sup 241}Am and {sup 235}U have been employed as back-to-back type double fission chambers. The present result at neutron energy of 0.0253 eV is 3.15 {+-} 0.097b. The ENDF/B-VI data is in good agreement with the present value, while the JENDL-3.2 data is lower by 4.2%. The evaluated data in JEF-2.2 and by Mughabghab are higher by 0.9% and 1.6%, respectively than the present result. The ratios of the earlier experimental data to the present value are distributed between 0.89 and 1.02. (author)}
place = {Japan}
year = {1997}
month = {Mar}
}
title = {Measurement of thermal neutron cross section for {sup 241}Am(n,f) reaction}
author = {Kobayashi, Katsuhei, Yamamoto, Shuji, Fujita, Yoshiaki, Miyoshi, Mitsuharu, Kimura, Itsuro, Kanno, Ikuo, and Shinohara, Nobuo}
abstractNote = {Making use of a standard neutron spectrum field with a pure Maxwellian distribution, the thermal neutron cross section for the {sup 241}Am(n,f) reaction has been measured relative to the reference value of 586.2b for the {sup 235U}(n,f) reaction. For the present measurement, electrodeposited layers of {sup 241}Am and {sup 235}U have been employed as back-to-back type double fission chambers. The present result at neutron energy of 0.0253 eV is 3.15 {+-} 0.097b. The ENDF/B-VI data is in good agreement with the present value, while the JENDL-3.2 data is lower by 4.2%. The evaluated data in JEF-2.2 and by Mughabghab are higher by 0.9% and 1.6%, respectively than the present result. The ratios of the earlier experimental data to the present value are distributed between 0.89 and 1.02. (author)}
place = {Japan}
year = {1997}
month = {Mar}
}