Abstract
The effective thermal neutron cross section of {sup 243}Am(n,{gamma}){sup 244}Am reaction was measured by the activation method. Highly-purified {sup 243}Am target was irradiated in an aluminum capsule by using a research reactor JRR-3M. The tentative effective thermal neutron cross sections are 3.92 b, and 84.44 b for the production of {sup 244g}Am and {sup 244m}Am, respectively. (author)
Hatsukawa, Yuichi;
Shinohara, Nobuo;
Hata, Kentaro
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Hatsukawa, Yuichi, Shinohara, Nobuo, and Hata, Kentaro.
Measurements of neutron cross section of the {sup 243}Am(n,{gamma}){sup 244}Am reaction.
Japan: N. p.,
1998.
Web.
Hatsukawa, Yuichi, Shinohara, Nobuo, & Hata, Kentaro.
Measurements of neutron cross section of the {sup 243}Am(n,{gamma}){sup 244}Am reaction.
Japan.
Hatsukawa, Yuichi, Shinohara, Nobuo, and Hata, Kentaro.
1998.
"Measurements of neutron cross section of the {sup 243}Am(n,{gamma}){sup 244}Am reaction."
Japan.
@misc{etde_300357,
title = {Measurements of neutron cross section of the {sup 243}Am(n,{gamma}){sup 244}Am reaction}
author = {Hatsukawa, Yuichi, Shinohara, Nobuo, and Hata, Kentaro}
abstractNote = {The effective thermal neutron cross section of {sup 243}Am(n,{gamma}){sup 244}Am reaction was measured by the activation method. Highly-purified {sup 243}Am target was irradiated in an aluminum capsule by using a research reactor JRR-3M. The tentative effective thermal neutron cross sections are 3.92 b, and 84.44 b for the production of {sup 244g}Am and {sup 244m}Am, respectively. (author)}
place = {Japan}
year = {1998}
month = {Mar}
}
title = {Measurements of neutron cross section of the {sup 243}Am(n,{gamma}){sup 244}Am reaction}
author = {Hatsukawa, Yuichi, Shinohara, Nobuo, and Hata, Kentaro}
abstractNote = {The effective thermal neutron cross section of {sup 243}Am(n,{gamma}){sup 244}Am reaction was measured by the activation method. Highly-purified {sup 243}Am target was irradiated in an aluminum capsule by using a research reactor JRR-3M. The tentative effective thermal neutron cross sections are 3.92 b, and 84.44 b for the production of {sup 244g}Am and {sup 244m}Am, respectively. (author)}
place = {Japan}
year = {1998}
month = {Mar}
}