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論文

Measurements of neutron total and capture cross sections of $$^{139}$$La and evaluation of resonance parameters

遠藤 駿典; 河村 しほり*; 奥平 琢也*; 吉川 大幹*; Rovira Leveroni, G.; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之

European Physical Journal A, 59(12), p.288_1 - 288_12, 2023/12

https://doi.org/10.1140/epja/s10050-023-01203-4
 被引用回数：0 パーセンタイル：0.02(Physics, Nuclear)

ランタン(La)-139の断面積と共鳴パラメータは、原子力分野への応用や基礎核物理の研究にとって重要である。本論文では、大強度陽子加速器施設(J-PARC)のANNRIにてLaの中性子全断面積と捕獲断面積を測定した。Negative共鳴を含む4つの共鳴の共鳴パラメータを、共鳴解析コードREFITを用いて求めた。その結果いくつかの共鳴パラメータにおいて、評価済み核データライブラリとの不一致が見られた。さらに全断面積を再現するために、スピン依存する散乱半径もフィットした。得られた散乱半径は、評価済み核データライブラリで記録されたものよりも大きいことがわかった。

論文

Development of correction method for sample density effect on PGA

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

Journal of Radioanalytical and Nuclear Chemistry, 332(8), p.2995 - 2999, 2023/08

https://doi.org/10.1007/s10967-023-08961-x
 被引用回数：0 パーセンタイル：0.01(Chemistry, Analytical)

The accuracy of the prompt $$gamma$$-ray analysis is known to degrade for the samples containing neutron-scattering materials, such as hydrogen, depending on its content. Recently, we discovered that the density of the scattering materials also affects the accuracy. In this paper, we developed a correction method for the effect of the sample densities. The developed correction method is straightforward and applicable to samples with unknown densities. The simulation and experiments verified the performance of the correction method. The results confirmed that the correction method could reduce the uncertainty due to sample density from 47% to approximately 1%.

論文

Neutron total and capture cross-section measurements of $$^{155}$$Gd and $$^{157}$$Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC$$cdot$$MLF$$cdot$$ANNRI

木村 敦; 中村 詔司; 遠藤 駿典; Rovira Leveroni, G.; 岩本 修; 岩本 信之; 原田 秀郎; 片渕 竜也*; 寺田 和司*; 堀 順一*; et al.

Journal of Nuclear Science and Technology, 60(6), p.678 - 696, 2023/06

https://doi.org/10.1080/00223131.2022.2134224
 被引用回数：2 パーセンタイル：53.91(Nuclear Science & Technology)

Neutron total and capture cross-section measurements of $$^{155}$$Gd and $$^{157}$$Gd were performed in the ANNRI at the MLF of the J-PARC. The neutron total cross sections were determined in the energy region from 5 to 100 meV. At the thermal neutron energy, the total cross sections were obtained to be 59.4$$pm$$1.7 and 251.9$$pm$$4.6 kilobarn for $$^{155}$$Gd and $$^{157}$$Gd, respectively. The neutron capture cross sections were determined in the energy region from 3.5 to 100 meV with an innovative method by taking the ratio of the detected capture event rate between thin and thick samples. At the thermal energy, the capture cross sections were obtained as 59.0$$pm$$2.5 and 247.4$$pm$$3.9 kilobarn for $$^{155}$$Gd and $$^{157}$$Gd, respectively. The present total and capture cross sections agree well within the standard deviations. The results for $$^{155}$$Gd were found to be consistent with the values in JENDL-4.0 and the experimental data given by Mastromarco et al. and Leinweber et al. within one standard deviation. Moreover, the present results for $$^{157}$$Gd agreed with the evaluated data in JENDL-4.0 and the experimental data by M${o}$ller et al. within one standard deviation and agreed with the data by Mastromarco et al. within 1.4 standard deviations. However, they disagree (11% larger) with the experimental result by Leinweber et al.

論文

J-PARC ANNRIビームラインにおける偏極熱外中性子利用

遠藤 駿典; 奥平 琢也*

波紋, 33(2), p.68 - 72, 2023/05

https://doi.org/10.5611/hamon.33.2_68

J-PARC・MLFに設置されている中性子ビームラインの一つであるANNRIでは、Ge検出器、NaI検出器、LaBr検出器などのガンマ線検出器を用いた核反応測定が行われている。さらに近年、偏極中性子生成デバイスであるHeスピンフィルタをANNRIにおいて導入可能となり、偏極中性子を用いた新たな核反応測定が行われるようになった。$$^{117}$$Snなどのp波共鳴において、中性子の偏極方向とガンマ線の放出方向に依存する断面積の測定が行われた。また偏極中性子と円偏光度測定を組み合わせた新たな核データや角相関項の測定が今後行われていく予定である。本稿ではこれらANNRIにおける偏極中性子利用に関しての現状について解説する。

論文

Covariance of resonance parameters ascribed to systematic uncertainties in experiments

遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.

EPJ Web of Conferences, 281, p.00012_1 - 00012_5, 2023/03

https://doi.org/10.1051/epjconf/202328100012

In resonance analysis, experimental uncertainties affect the accuracy of resonance parameters. A resonance analysis code REFIT can consider the statistical uncertainty of the experimental data in evaluation of the resonance parameter uncertainty. On the other hand, since the systematic uncertainties of the sample thickness and normalization, which is proportional to the cross-section, are not independent at each measurement point, they must be treated differently from the statistical uncertainty. However, their treatment has not been discussed in detail so far. In this study, we evaluated the effect of the systematic uncertainties of experimental data on deduced resonance parameters by varying sample-thickness values used for the REFIT code. Covariance of resonance parameters ascribed to systematic uncertainties were evaluated from the neutron transmission data of natural zinc measured at the J-PARC MLF ANNRI. We will introduce this evaluation method and discuss the feature of obtained correlations.

論文

Measurements of the neutron total and capture cross sections and derivation of the resonance parameters of $$^{181}$$Ta

遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.; 藤 暢輔; 瀬川 麻里子; 前田 亮

Nuclear Science and Engineering, 18 Pages, 2023/00

https://doi.org/10.1080/00295639.2023.2227826
 被引用回数：1 パーセンタイル：72.91(Nuclear Science & Technology)

The neutron transmission ratio and capture yield for $$^{181}$$Ta were measured in J-PARC MLF ANNRI to improve the accuracy of resonance parameters. The total cross section was determined from the transmission ratio in the energy range from 0.2 to 150 eV. The capture cross section was obtained from the capture yield using the pulse height weighting technique (PHWT) in the energy range from thermal to 150 eV. The obtained transmission ratio and capture cross-section were fitted by the resonance analysis code, REFIT, and the resonance parameters were determined below 150 eV. It was also discussed the correlations caused by fitting based on statistical uncertainty and correlations for systematic uncertainty based on sample thickness in the transmission measurements.

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

https://doi.org/10.1103/PhysRevC.106.064601
 被引用回数：2 パーセンタイル：52.69(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

https://doi.org/10.1038/s41598-022-08594-2
 被引用回数：2 パーセンタイル：31.9(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

Angular distribution of $$gamma$$ rays from the $$p$$-wave resonance of $$^{118}$$Sn

古賀 淳*; 高田 秀佐*; 遠藤 駿典; 藤岡 宏之*; 広田 克也*; 石崎 貢平*; 木村 敦; 北口 雅暁*; 新實 裕大*; 奥平 琢也*; et al.

Physical Review C, 105(5), p.054615_1 - 054615_5, 2022/05

https://doi.org/10.1103/PhysRevC.105.054615
 被引用回数：3 パーセンタイル：66.85(Physics, Nuclear)

J-PACR MLFのパルス中性子源及びBL04 ANNRIに設置されたゲルマニウム検出器を用いて、$$^{117}$$Sn(n,$$gamma$$)反応により生じるガンマ線の中性子エネルギー依存する角度分布を測定した。$$^{117}$$Snの複合核状態から$$^{118}$$Snの基底状態への遷移で発生する9327keVのガンマ線に関して、角度によって1.33eVの$$p$$波共鳴の形状が変わることが明らかに確認できた。この共鳴の低エネルギー側の積分値と高エネルギー側の積分値をそれぞれ$$N_{L}, N_{H}$$で表したとき、非対称性$$A_{LH}=(N_{L}-N_{H})/(N_{L}+N_{H})$$は$$A$$cos$$theta_{gamma}+B$$という角度依存をし、それぞれのパラメータ値が$$A=0.394pm0.073$$、$$B=0.118pm0.029$$であることがわかった。

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

https://doi.org/10.1016/j.anucene.2021.108828
 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

https://doi.org/10.1080/00223131.2021.1970040
 被引用回数：5 パーセンタイル：65.59(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

https://doi.org/10.1080/00223131.2021.1954104
 被引用回数：3 パーセンタイル：45.99(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

https://doi.org/10.1021/acs.analchem.1c01233
 被引用回数：4 パーセンタイル：24.69(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

https://doi.org/10.1080/00223131.2020.1864492
 被引用回数：2 パーセンタイル：31.78(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

https://doi.org/10.1103/PhysRevC.103.045801
 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

https://doi.org/10.1080/00223131.2019.1598508
 被引用回数：14 パーセンタイル：84.54(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

https://doi.org/10.1093/ptep/ptz002
 被引用回数：32 パーセンタイル：87.41(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

https://doi.org/10.1080/00223131.2018.1485519
 被引用回数：18 パーセンタイル：88.27(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

https://doi.org/10.1088/1748-0221/13/02/P02018
 被引用回数：6 パーセンタイル：31.02(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

https://doi.org/10.11484/jaea-conf-2017-001

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.

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