Measurement of the thermal neutron capture-cross section of 191Ir at ANNRI MLF J-PARC

被引:0
|
作者
Patwary, Md Kawchar Ahmed [3 ]
Segawa, Mariko [1 ]
Maeda, Makoto [1 ]
Toh, Yosuke [1 ]
Endo, Shunsuke [2 ]
Nakamura, Shoji [2 ]
Rovira, Gerard [2 ]
Kimura, Atsushi [2 ]
机构
[1] Res Grp Nucl Sensing, Japan Atom Energy Agcy, Ibaraki, Japan
[2] Nucl Data Ctr, Japan Atom Energy Agcy, Ibaraki, Japan
[3] Japan Atom Energy Agcy, Res Grp Nucl Sensing, 2-4 Shirakata,Tokai mura, Ibaraki 3191195, Japan
关键词
Ir-192; radionuclide; high-dose-rate brachytherapy; Ir-191(n; gamma)Ir-192; reaction; neutron time-of-flight method; pulse height weighting technique; ANNRI; MLF; J-PARC; thermal neutron capture cross section; INDUCED NUCLEAR-REACTIONS; LONG-LIVED PRODUCTS; CYCLOTRON PRODUCTION; EXCITATION-FUNCTIONS; BRACHYTHERAPY; PLATINUM; SYSTEM;
D O I
10.1080/00223131.2024.2334757
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The neutron capture cross section of Am-243 was measured by the time-of-flight method with a pulsed neutron beam from a spallation neutron source of the Japan Proton Accelerator Research Complex. An Fe neutron beam filter was used to make the incident neutron beam quasi-monoenergetic around 23.5 keV. The neutron capture gamma-rays were detected with a NaI(Tl) detector. The pulse height weighting technique was employed to derive the neutron capture cross section from the pulse height spectrum. The cross section was determined relative to the capture cross section of 197Au of JENDL-4.0. The obtained neutron capture cross section of Am-243 was 2.52 +/- 0.14 b, determined with a much smaller uncertainty than those of past measurements.
引用
收藏
页码:1385 / 1396
页数:12
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