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Am neutron-induced capture cross section measurement with a large coverage HPGe detector at ANNRI/J-PARCLeong, L.; 木村 敦; 中村 詔司; 岩本 修; 原田 秀郎
JAEA-Conf 2015-003, P. 235, 2016/03
Neutron-induced cross sections of Minor Actinides are needed data for neutron-based applications like nuclear reactors. ANNRI is a neutron facility, which delivers neutrons produced by spallation at the MLF/J-PARC. The neutron spectrum of ANNRI spans from thermal to intermediate energies. In addition, due to the high power. It achieves the highest flux of this spectrum compared to other facilities. Therefore, it is a well-suited facility for neutron cross section measurements. Am (n,
) cross section was measured at ANNRI using the TOF method. In this experiment, we used HPGe detectors that covered a substantial fraction of the solid angle. Ge detectors can achieve a very high energy resolution. In this work, we focused the analysis on the capture rate to extract the corresponding cross section. We will show how the detection efficiency, the dead time correction, and the background estimation were estimated to derive the capture yield.
Ni caseLeong, L.; 木村 敦; 原田 秀郎; 中村 詔司; 岩本 修
EPJ Web of Conferences, 93, p.06005_1 - 06005_2, 2015/05
被引用回数：0 パーセンタイル：0.16(Physics, Multidisciplinary)ANNRI is an outstanding neutron facility at J-PARC delivering intense pulsed neutrons produced by spallation neutrons. The Ni(n,) reaction cross section has been measured at ANNRI. The detection was done by several HPGe detectors covering a substantial fraction of the solid angle. We focused the analysis on the capture rate to extract the corresponding cross section. We will show how the detection efficiency, the dead time correction, the background estimation, and the normalization have been estimated to get an accurate capture yield. Finally, the Ni capture cross section in the thermal and epithermal energy domains (0.001 eV to 1 keV), will be reported and compared to recent evaluations.
Leong, L.; 佐藤 達彦; 木村 敦; 岩本 修; 原田 秀郎
no journal, ,
Minor Actinides (MAs) are produced abundantly in the nuclear reactor. Most of them are considered as high radioactive waste. Transmutation technology is an issue to convert these radioactive MAs to stable state and it require the very accurate nuclear data of the MAs. Am-243 (n,g) capture cross section was recently measured at ANNRI. In order to achieve the accurate cross section measurement, we need to estimate the background due to the self-shielding and the multiple-scattering effects. In this work, we studied specifically the impacts of these effects for the purpose of estimating the background, using Monte Carlo simulation PHITS. In fact, due to the high neutron absorption, these two effects in the Am-243 capture cross section measurement in resonance region are large and lead a high uncertainty on the data. As these backgrounds are difficult to be estimated by experiment, therefore we corrected these two effects and eventually conciliated the percent uncertainties in resonance region.
