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論文

Measurement of the transverse asymmetry of $$gamma$$ rays in the $$^{117}$$Sn($$n,gamma$$)$$^{118}$$Sn reaction

遠藤 駿典; 奥平 琢也*; 安部 亮太*; 藤岡 宏之*; 広田 克也*; 木村 敦; 北口 雅暁*; 奥 隆之; 酒井 健二; 嶋 達志*; et al.

Physical Review C, 106(6), p.064601_1 - 064601_7, 2022/12

 被引用回数:0 パーセンタイル:0.02(Physics, Nuclear)

熱外中性子入射により形成される複合核において観測された、空間反転対称性の破れの大きな増幅は、今のところ複合核状態の入射チャネルにおけるパリティの異なる部分波の混合の結果として説明されている。さらに時間反転対称性の破れも同様のメカニズムで増幅されることが示唆されている。この入射チャネルにおける混合は、複合核共鳴から放出される個々のガンマ線のエネルギー依存なスピン-角相関を引き起こす。本研究ではJ-PARC・MLF・ANNRIにて偏極熱外中性子ビームを用い、$$^{117}$$Sn($$n,gamma$$)$$^{118}$$Sn反応におけるガンマ線強度分布が、中性子の偏極方向に依存することを確認した。

論文

Effect of sample density in prompt $$gamma$$-ray analysis

前田 亮; 瀬川 麻里子; 藤 暢輔; 遠藤 駿典; 中村 詔司; 木村 敦

Scientific Reports (Internet), 12(1), p.6287_1 - 6287_8, 2022/06

 被引用回数:1 パーセンタイル:0(Multidisciplinary Sciences)

A high-accuracy analytical method is broadly required to obtain reliable research results. Thus, prompt $$gamma$$-ray analysis (PGA), one of the most accurate non-destructive analytical methods, has been employed in various fields. However, the measurement accuracy of PGA is also known to degrade in hydrogenous samples. The degradation is caused by variation in the measurement sensitivity (counts per milligram) following the change in neutron energy due to scattering with hydrogen nucleus. Number of scatterings is well known to depend on the hydrogen content in a sample. However, considering multiple scatterings, hydrogen density, which has not been taken into account as yet, may also lead to the accuracy degradation. In this research, the effect of the hydrogen density in PGA is investigated by evaluating the measurement sensitivity of samples with the same hydrogen content and different densities. The results showed that the measurement sensitivity varies by more than 30% depending on the hydrogen density even at the same hydrogen content. The variation is a particularly serious problem for PGA requiring a few percent accuracy in most cases. Additionally, although the variation is apparently observed in hydrogenous samples, the similar phenomenon can occur in other nuclides with a large scattering cross section; it may affect nuclear cross-section measurements using neutrons in such fields as astrophysics and nuclear energy.

論文

Investigation of radioactive samples for neutron capture reaction measurements using energy-resolved neutron imaging

瀬川 麻里子; 藤 暢輔; 甲斐 哲也; 木村 敦; 中村 詔司

Annals of Nuclear Energy, 167, p.108828_1 - 108828_5, 2022/03

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

To obtain accurate analytical results via neutron-capture reactions, the effects of sample shapes must be considered. However, the estimations of the effects were difficult to verify in some cases such as sealed samples and valuable objects. In this study, the shape effects for sealed radioactive samples were estimated experimentally. The significant localization of the $$^{129}$$I sample was confirmed only by an energy-resolved neutron imaging. It is revealed that the shape effect was necessary to be corrected at the neutron resonance peaks. Consequently, we conclude that the energy-resolved neutron imaging will be quite effective to improve the analytical accuracy.

論文

Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV

遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.; 寺田 和司*; 明午 伸一郎; 藤 暢輔; 瀬川 麻里子; et al.

Journal of Nuclear Science and Technology, 59(3), p.318 - 333, 2022/03

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

In order to improve the accuracy of the cross-section and the resonance parameters of $$^{93}$$Nb, neutron capture and total cross-sections were measured using the J-PARC MLF ANNRI. The thermal-neutron capture cross-section was deduced as 0.97$$pm$$0.12 b. The resonance parameters of 11 resonances below 400 eV were determined from obtained capture cross-sections and transmission ratios by using the resonance analysis code, REFIT.

論文

KeV-region analysis of the neutron capture cross-section of $$^{237}$$Np

Rovira Leveroni, G.; 片渕 竜也*; 登坂 健一*; 松浦 翔太*; 児玉 有*; 中野 秀仁*; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之

Journal of Nuclear Science and Technology, 59(1), p.110 - 122, 2022/01

 被引用回数:1 パーセンタイル:33.13(Nuclear Science & Technology)

Neutron capture cross-section measurements for $$^{237}$$Np have been conducted with the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Materials and Life Science Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC) using neutrons with energy ranging from thermal energy to 1 MeV. A Time of Flight (TOF) method using a NaI(Tl) detector was employed for these measurements and the data were analyzed based on the pulse-height weighting technique in order to derive the neutron capture cross-section. The absolute capture cross-section was determined using the whole shape of the first resonance from JENDL-4.0 together with the total neutron flux derived from a $$^{197}$$Au sample measurement in which the first resonance was completely saturated. Both normalization techniques present agreement within 2%. The present results are also compared evaluated data libraries. There is a discrepancy of 10-25% discrepancy from 0.5 to 20 keV with JENDL-4.0. Nonetheless, above this energy, the JENDL-4.0 seems to reproduce the present data better as the results agree within uncertainties up to 500 keV. The cross-section results contain errors below 4% from 0.5 to 30 keV. However, the total uncertainty increases to over 8% over that energy. Along with the cross section measurement, theoretical calculations were performed to reproduce the present results.

論文

Nondestructive quantitative analysis of difficult-to-measure radionuclides $$^{107}$$Pd and $$^{99}$$Tc

藤 暢輔; 瀬川 麻里子; 前田 亮; 常山 正幸*; 木村 敦; 中村 詔司; 遠藤 駿典; 海老原 充*

Analytical Chemistry, 93(28), p.9771 - 9777, 2021/07

 被引用回数:2 パーセンタイル:35(Chemistry, Analytical)

Considering the expanding demand for nuclear waste management of the spent nuclear fuel materials in near future, a non-destructive analytical scheme applicable to the most difficult-to-measure nuclide of $$^{107}$$Pd, which emits no decay gamma-rays and whose half-life is too long to be decayed out during a human lifetime, was designed. The scheme consists of a sophisticated instrument capable of the detection of gamma-rays by Ge detectors coupled with time-of-flight measurement of neutrons and a high-intensity pulsed neutron beam, and can simultaneously perform TOF-coupled prompt gamma-ray analysis (TOF-PGA) as well as PGA and NRCA. An analytical capability was evaluated by applying to simulated samples of the Tc-platinum group metals (Tc-PGMs) obtained by the group partitioning process of spent nuclear fuels, which contain not only $$^{107}$$Pd but also $$^{99}$$Tc and another difficult-to-measure fission product. It was confirmed that, although PGA and NRCA could accurately analyze both nuclides in individual single substances, only TOF-PGA can analyze $$^{107}$$Pd as well as $$^{99}$$Tc in the Tc-PGMs simulated sample. The TOF-PGA measurement technique can be widely used for the non-destructive analysis of $$^{107}$$Pd and $$^{99}$$Tc in nuclear wastes.

論文

Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC

川瀬 頌一郎*; 木村 敦; 原田 秀郎; 岩本 信之; 岩本 修; 中村 詔司; 瀬川 麻里子; 藤 暢輔

Journal of Nuclear Science and Technology, 58(7), p.764 - 786, 2021/07

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

The neutron capture cross sections of $$^{244}$$Cm and $$^{246}$$Cm were measured for the neutron energy range of 1-1000 eV via the neutron time-of-flight method with ANNRI at MLF of the J-PARC. The world's most intense neutron pulses from the Japan Spallation Neutron Source enable the accurate measurement of neutron capture cross sections. Besides, single-bunched neutron pulses allow the analysis in a higher neutron energy region than the previous measurement at ANNRI. The resonance analyses were performed up to 1000 eV by using a resonance shape analysis code REFIT. The spectra of prompt gamma-rays from neutron capture reactions of $$^{244}$$Cm and $$^{246}$$Cm were also obtained, and 43 and 10 prompt gamma-ray peaks from $$^{244}$$Cm(n,$$gamma$$) and $$^{246}$$Cm(n,$$gamma$$) reactions were newly observed, respectively.

論文

Isomer production ratio of the $$^{112}$$Cd($$n,gamma$$)$$^{113}$$Cd reaction in an $$s$$-process branching point

早川 岳人*; 藤 暢輔; 木村 敦; 中村 詔司; 静間 俊行*; 岩本 信之; 千葉 敏*; 梶野 敏貴*

Physical Review C, 103(4), p.045801_1 - 045801_5, 2021/04

 被引用回数:0 パーセンタイル:0.02(Physics, Nuclear)

A $$beta$$-decay unstable isomer with a half-life of 14.1 y at 264 keV in $$^{113}$$Cd is a branching point in the $$s$$ process, from which a weak branch reaches to a rare tin isotope $$^{115}$$Sn whose astrophysical origin has been an open problem. We have measured $$gamma$$ rays decaying to the ground state or the isomer in the $$^{112}$$Cd($$n,gamma$$)$$^{113}$$Cd reaction using high-energy resolution detectors in conjunction with a time-of-flight method. The relative production ratios of the isomer to the total following the neutron capture reactions on $$^{112}$$Cd have been evaluated in an energy region of up to 9 keV, and the spin and parity of several resonances have been assigned.

論文

Measurements of the $$^{243}$$Am neutron capture and total cross sections with ANNRI at J-PARC

木村 敦; 中村 詔司; 寺田 和司*; 中尾 太郎*; 水山 一仁*; 岩本 信之; 岩本 修; 原田 秀郎; 片渕 竜也*; 井頭 政之*; et al.

Journal of Nuclear Science and Technology, 56(6), p.479 - 492, 2019/06

 被引用回数:9 パーセンタイル:76.35(Nuclear Science & Technology)

Neutron total and capture cross sections of $$^{243}$$Am have been measured in Accurate Neutron Nucleus Reaction measurement Instrument at Materials and Life Science Experimental Facility of Japan Proton Accelerator Research Complex with a neutron TOF method. The neutron capture cross section in the energy region from 10 meV to 100 eV was determined using an array of Ge detectors. Three samples with different activities were used for measurements of the capture cross section. The neutron total cross section in the energy region from 4 meV to 100 eV was measured using Li-glass detectors. Derived cross-section value at neutron energy of 0.0253 eV is 87.7$$pm$$5.4 b for the capture cross section and 101$$pm$$11 b for the total cross section.

論文

Gamma-ray spectrum from thermal neutron capture on gadolinium-157

萩原 開人*; 矢野 孝臣*; Das, P. K.*; Lorenz, S.*; 王 岩*; 作田 誠*; 木村 敦; 中村 詔司; 岩本 信之; 原田 秀郎; et al.

Progress of Theoretical and Experimental Physics (Internet), 2019(2), p.023D01_1 - 023D01_26, 2019/02

 被引用回数:23 パーセンタイル:86.37(Physics, Multidisciplinary)

We have measured the $$gamma$$-ray energy spectrum from the thermal neutron capture, $$^{157}Gd(n,gamma)^{158}Gd$$, on an enriched $$^{157}$$Gd target ($$Gd_2O_3$$) in the energy range from 0.11 MeV up to about 8 MeV. The target was placed inside the germanium spectrometer of the ANNRI detector at J-PARC and exposed to a neutron beam from the Japan Spallation Neutron Source (JSNS). Radioactive sources ($$^{60}$$Co, $$^{137}$$Cs, and $$^{152}$$Eu) and the reaction $$^{35}Cl(n,gamma)$$ were used to determine the spectrometer's detection efficiency for $$gamma$$ rays at energies from 0.3 to 8.5 MeV. Using a Geant4-based Monte Carlo simulation of the detector and based on our data, we have developed a model to describe the $$gamma$$-ray spectrum from the thermal $$^{157}Gd(n,gamma)^{158}Gd$$ reaction. While we include the strength information of 15 prominent peaks above 5 MeV and associated peaks below 1.6 MeV from our data directly into the model, we rely on the theoretical inputs of nuclear level density and the photon strength function of $$^{158}$$Gd to describe the continuum $$gamma$$-ray spectrum from the $$^{157}Gd(n,gamma)^{158}Gd$$ reaction. The results of the comparison between the observed $$gamma$$-ray spectra from the reaction and the model are reported in detail.

論文

Measurements of neutron total and capture cross sections of $$^{241}$$Am with ANNRI at J-PARC

寺田 和司*; 木村 敦; 中尾 太郎*; 中村 詔司; 水山 一仁*; 岩本 信之; 岩本 修; 原田 秀郎; 片渕 竜也*; 井頭 政之*; et al.

Journal of Nuclear Science and Technology, 55(10), p.1198 - 1211, 2018/10

AA2017-0628.pdf:2.06MB

 被引用回数:14 パーセンタイル:85.76(Nuclear Science & Technology)

Neutron total and capture cross sections of $$^{241}$$Am have been measured with a new data acquisition system and a new neutron transmission measurement system installed in Accurate Neutron Nucleus Reaction measurement Instrument (ANNRI) at Materials and Life Science Experimental Facility (MLF) of Japan Proton Accelerator Research Complex (J-PARC). The neutron total cross sections of $$^{241}$$Am were determined by using a neutron time-of-flight method in the neutron energy region from 4 meV to 2 eV. The thermal total cross section of $$^{241}$$Am was derived with an uncertainty of 2.9%. A pulse-height weighting technique was applied to determine neutron capture yields of $$^{241}$$Am. The neutron capture cross sections were determined by the time-of-flight method in the neutron energy region from the thermal to 100 eV, and the thermal capture cross section was obtained with an uncertainty of 4.1%. The evaluation data of JENDL-4.0 and JEFF-3.2 were compared with the present results.

論文

Characterization of germanium detectors for the measurement of the angular distribution of prompt $$gamma$$-rays at the ANNRI in the MLF of the J-PARC

高田 秀佐*; 奥平 琢也*; 後藤 文也*; 広田 克也*; 木村 敦; 北口 雅暁*; 古賀 淳*; 中尾 太郎*; 酒井 健二; 清水 裕彦*; et al.

Journal of Instrumentation (Internet), 13(2), p.P02018_1 - P02018_21, 2018/02

 被引用回数:5 パーセンタイル:31.33(Instruments & Instrumentation)

In this study, the germanium detector assembly, installed at the Accurate Neutron Nuclear Reaction measurement Instruments (ANNRI) in the Material and Life Science Facility (MLF) operated by the Japan Proton Accelerator Research Complex (J-PARC), has been characterized for extension to the measurement of the angular distribution of individual $$gamma$$-ray transitions from neutron-induced compound states. We have developed a Monte Carlo simulation code using the GEANT4 toolkit, which can reproduce the pulse-height spectra of $$gamma$$-rays from radioactive sources and (n,$$gamma$$) reactions. The simulation is applicable to the measurement of $$gamma$$-rays in the energy region of 0.5-11.0 MeV.

論文

Measurement of the neutron capture cross-section of $$^{133}$$Cs as a part of the ImPACT project

Hales, B. P.; 中村 詔司; 木村 敦; 岩本 修

JAEA-Conf 2017-001, p.199 - 203, 2018/01

As part of the ImPACT project, it is currently planned to measure the neutron cross-section of $$^{135}$$Cs (half-life $$2.3 times 10^6$$ y), a long-lived fission product (LLFP), via neutron time-of-flight (TOF) method at the Japan Proton Accelerator Research Complex (J-PARC). Both $$^{133}$$Cs (natural Cs, stable) and $$^{137}$$Cs (half-life $$30.0$$ y) are unavoidable contaminants in the $$^{135}$$Cs sample. In working towards the measurement of $$^{135}$$Cs, a measurement of non-radioactive $$^{133}$$Cs has been conducted. The neutron capture cross-section of $$^{133}$$Cs in the thermal to epithermal energy region was experimentally measured via neutron TOF method at J-PARC. Measured results show good agreement with JENDL in the energy region below 10 eV.

論文

Neutron capture cross section measurements of $$^{120}$$Sn, $$^{122}$$Sn and $$^{124}$$Sn with the array of Ge spectrometer at the J-PARC/MLF/ANNRI

木村 敦; 原田 秀郎; 中村 詔司; 藤 暢輔; 井頭 政之*; 片渕 竜也*; 水本 元治*; 堀 順一*

EPJ Web of Conferences, 146, p.11031_1 - 11031_4, 2017/09

 被引用回数:0 パーセンタイル:0.08

Accurate neutron capture cross section data of $$^{126}$$Sn, which is one of the most important long-lived fission products (LLFPs), is required in the study of transmutation of radioactive waste. However, there is only one experimental data at the thermal energy. A $$^{126}$$Sn sample for a nuclear data experiment contaminated with a large amount of tin stable isotopes, $$^{115, 117-120, 122, 124}$$Sn, because these stable isotopes also have fission yields. These isotopes have large effects on neutron-capture cross-section measurements for $$^{126}$$Sn. To obtain accurate cross-section data for $$^{126}$$Sn, a series of neutron-capture cross-section measurements of all the tin stable isotopes are required. Therefore, the measurements of all tin stable isotopes have been started with Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI) of Materials and Life science experimental Facility (MLF) in Japan Proton Accelerator Research Complex (J-PARC). In this presentation, preliminary results of the neutron-capture cross-section measurements of $$^{120, 122, 124}$$Sn are reported in the neutron energy region from 10 meV to 2 keV.

論文

Development of a correction method for the time-of-flight prompt $$gamma$$-ray analysis

Huang, M.; 藤 暢輔; 海老原 充*; 木村 敦; 中村 詔司

Journal of Applied Physics, 121(10), p.104901_1 - 104901_7, 2017/03

 被引用回数:2 パーセンタイル:11.38(Physics, Applied)

A new analytical technique, time-of-flight prompt $$gamma$$-ray analysis, has been developed at the Japan Proton Accelerator Research Complex. In order to apply it to accurate elemental analysis, a set of standard Fe and Au samples were measured to examine the factors which affect the number of detected events. It was found that the main contributing factors included the attenuations of neutrons and $$gamma$$ rays in the sample, live-time ratio of the data acquisition system and signal pile-up correction factor. A simulation model was built for the estimations of neutron and $$gamma$$-ray attenuations. A simple empirical formula was proposed to calculate the signal pile-up correction factor. The whole correction method has proven to be accurate and reliable.

論文

Measurement of the isomer production ratio for the $$^{112}$$Cd($$n,gamma$$)$$^{113}$$Cd reaction using neutron beams at J-PARC

早川 岳人*; 藤 暢輔; Huang, M.; 静間 俊行*; 木村 敦; 中村 詔司; 原田 秀郎; 岩本 信之; 千葉 敏*; 梶野 敏貴*

Physical Review C, 94(5), p.055803_1 - 055803_6, 2016/11

 被引用回数:4 パーセンタイル:36.4(Physics, Nuclear)

The astrophysical origin of a rare isotope $$^{115}$$Sn has remained still an open question. An isomer ($$T_{1/2}$$=14.1 y) in $$^{113}$$Cd is an s-process branching point from which a nucleosynthesis flow reaches to $$^{115}$$Sn. The $$s$$-process abundance of $$^{115}$$Sn depends on the isomer production ratio in the $$^{112}$$Cd($$n,gamma$$)$$^{113}$$Cd reaction. However, the ratio has not been measured in an energy region higher than the thermal energy. We have measured $$gamma$$ rays following neutron capture reactions on $$^{112}$$Cd using two cluster HPGe detectors in conjunction with a time-of-flight method at J-PARC. We have obtained the result that the relative $$gamma$$-ray intensity ratio of the isomer is almost constant in an energy region of up to 5 keV. This result suggests that the $$s$$-process contribution to the solar abundance of $$^{115}$$Sn is negligibly small. We have found that the ratio of a resonance at 737 eV shows about 1.5 times higher than other ratios. This enhancement can be explained by a $$p$$-wave neutron capture. This result suggests measurements of decay $$gamma$$ rays to isomers are effective to assign the spin and parity for neutron capture resonances.

論文

「第5回ANNRI研究会」会議報告

中村 詔司; 藤 暢輔; 木村 敦; 片渕 竜也*

核データニュース(インターネット), (115), p.49 - 60, 2016/10

2016年8月4日、東京工業大学先導原子力研究所にて開催された「第5回ANNRI研究会」の会議内容について報告するものである。本研究会は、日本原子力研究開発機構(JAEA)原子力基礎工学研究センター、J-PARCセンター(JAEA & KEK)、東京工業大学先導原子力研究所、及び首都大学東京との共同主催にて開催された。本研究会では、ANNRIにより切り拓かれつつある研究を中心に、関連する分野の最前線の研究成果について講演頂き、専門分野を超えて議論すると共に今後の利用を推進する上での課題や必要な取組について討議された。また、今回はANNRI建設にご尽力頂いた東京工業大学井頭政之教授の特別講演も併せて開催された。

論文

J-PARC/ANNRIにおける即発$$gamma$$線分析法開発

藤 暢輔; 海老原 充*; Huang, M.; 木村 敦; 中村 詔司; 原田 秀郎

放射化学, (33), p.1 - 9, 2016/03

中性子即発$$gamma$$線分析(PGA)は、中性子捕獲反応に伴って放出される即発$$gamma$$線により元素分析を行う方法で、迅速に多元素を非破壊分析できるという特長がある。そのため、宇宙化学・環境・考古学・材料など幅広い分野で用いられ、多くの研究に貢献している。PGAはこれまでに同時計数法や反同時計数法によって検出限界や峻別性能の改良がおこなわれてきたが、大強度陽子加速器施設(J-PARC)の物質・生命科学実験施設(MLF)における大強度パルス中性子ビームによって、飛行時間法を用いた即発$$gamma$$線分析(TOF-PGA)の利用が可能となった。本稿では同時計数法による即発$$gamma$$線分析(MPGA)のほか、MLFに設置された中性子核反応測定装置(ANNRI)の概要と本装置によって可能となるTOF-PGAについて解説する。

論文

Current activities and future plans for nuclear data measurements at J-PARC

木村 敦; 原田 秀郎; 中村 詔司; 岩本 修; 藤 暢輔; 小泉 光生; 北谷 文人; 古高 和禎; 井頭 政之*; 片渕 竜也*; et al.

European Physical Journal A, 51(12), p.180_1 - 180_8, 2015/12

 被引用回数:1 パーセンタイル:16.45(Physics, Nuclear)

In order to improve the data accuracy of neutron-capture cross sections of minor actinides (MAs) and long-lived fission products (LLFPs), a new experimental instrument named "Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI)" has been constructed in the Materials and Life science experimental Facility (MLF) at the Japan Proton Accelerator Research Complex (J-PARC), and measurements of neutron-capture cross sections of MAs, LLFPs and some stable isotopes with high intensity pulsed neutrons have been started. The analyses for $$^{244}$$Cm, $$^{246}$$Cm, $$^{241}$$Am and $$^{237}$$Np were finished; those for $$^{129}$$I, $$^{107}$$Pd, $$^{99}$$Tc, $$^{93}$$Zr and some stable isotopes are in progress. These results will make significant contributions in the field of developing innovative nuclear systems.

論文

BL04「ANNRI」における元素分析法の開発

藤 暢輔; Huang, M.; 木村 敦; 中村 詔司; 原田 秀郎; 海老原 充*

四季, 28, P. 4, 2015/09

中性子核反応測定装置ANNRIは、高検出効率の即発$$gamma$$線検出装置、高性能なデータ収集系等を備えているほか、広いエネルギーレンジの中性子を用いることができる。中性子を用いた非破壊分析法の一つである即発$$gamma$$線分析(PGA)は、非破壊・多元素同時・バルク分析などの特徴を持つため貴重な試料や破壊が困難な試料の分析に有効である。ANNRIではパルス中性子を用いることができるため、中性子捕獲反応における共鳴を使った分析(中性子共鳴捕獲分析法)も行うことができる。物質・生命科学実験施設MLFから得られる大強度パルス中性子と大立体角を持つゲルマニウム検出器等を用いることによってゲルマニウム検出器でも中性子共鳴捕獲分析を行うことを可能とし、2つの手法を融合した新しい手法を確立した。これによってPGAと中性子共鳴捕獲分析の2つの結果が同時に得られるだけでなく、2つの分析手法の融合による相乗効果が得られる。つまり、PGAでも中性子共鳴捕獲分析でも測定が困難であるものでも分析できるようになった。本論文では、開発した手法について混合標準試料を用いた実験をもとにその特長についての解説を行う。

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