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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

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

第35回NEA核データ評価国際協力ワーキングパーティ(WPEC)会合報告

岩本 修; 岩本 信之; 木村 敦; 多田 健一; 横山 賢治

核データニュース(インターネット), (136), 6 Pages, 2023/10

OECD/NEA/NSC主催のWPEC(Working Party on International Nuclear Data Evaluation Co-operation)の本会合及び関連するサブグループ(SG)、専門家グループ(EG)会合が、2023年5月15日$$sim$$5月17日の日程で、NEA本部とWebでのハイブリッド形式によって実施された。日本からは2名(岩本(修)、多田)が対面で、その他がオンラインで参加した。日本を含め、米国や欧州、中国、IAEA、NEAから出席があり、対面でのWPEC本会合への参加は30名程度であった。以下に、核データ測定、評価及びEG、SGの活動状況について報告する。

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

 被引用回数:2 パーセンタイル:56.43(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

General-purpose nuclear data library JENDL-5 and to the next

岩本 修; 岩本 信之; 国枝 賢; 湊 太志; 中山 梓介; 木村 敦; 中村 詔司; 遠藤 駿典; 長家 康展; 多田 健一; et al.

EPJ Web of Conferences, 284, p.14001_1 - 14001_7, 2023/05

Japanese Evaluated Nuclear Data Library version 5 (JENDL-5) was released in 2021. JENDL-5 is intended to extend its generality from JENDL-4.0 by covering a wide variety of nuclear data for applications not only to nuclear design and decommissioning, but also to radiation-related fields. Overview of JENDL-5 and a future plan for the next of JENDL-5 are presented. JENDL-5 includes up-to-date neutron reaction cross sections incorporating other various types of data such as newly evaluated nuclear decay, fission yield, and thermal neutron scattering law. The neutron induced reaction cross sections especially on minor actinides in the resonance regions are improved by the experimental data measured at ANNRI. The extensive benchmark analyses on neutron nuclear data were made and the performance of JENDL-5 was confirmed by benchmark tests of ICSBEP and IRPhEP as well as fast reactors, radiation shielding calculations, and so on. So far, several JENDL special-purpose files have been developed for various applications. The data cover neutron, charged particles, and photon induced reactions. As the neutron induced reaction files, two special purpose files of JENDL/AD-2017 and JENDL/ImPACT-2018 were released to meet needs of nuclear backend applications including activation evaluation for nuclear facilities and nuclear transmutations of high-level radioactive wastes of long-lived fission products, respectively. Furthermore, the photon, proton and deuteron data were released as JENDL/PD-2016.1, JENDL-4.0/HE and JENDL/DEU-2020, respectively, for accelerator applications. With updating the data, they were incorporated in JENDL-5 as sub-libraries for facilitation of usability of JENDL. As the next step of JENDL-5, provision of the proper and sufficient covariance will be a major challenge, where cross correlations across different reactions or data-types may play a significant role in connection with data assimilation for various applications.

論文

Simultaneous evaluation of uranium and plutonium fast neutron fission cross sections up to 200 MeV for JENDL-5 and its updates

大塚 直彦*; 岩本 修

EPJ Web of Conferences, 284, p.08011_1 - 08011_4, 2023/05

The fast neutron fission cross sections of $$^{233,235,238}$$U and $$^{239,240,241}$$Pu were evaluated for the JENDL-5 library up to 200 MeV. The experimental fission cross sections and their ratios in the EXFOR library were reviewed with the source articles. Additionally, Poenitz's data compiled in his GMA database were reviewed. We found about $$^{16}$$0 datasets are archived with the uncertainty information sufficient for covariance matrix construction and converted them from EXFOR to an experimental database with their covariance matrices. When the uncertainty information in the source article is missing in the EXFOR entry, we updated the EXFOR entry. We minimized corrections to the experimental database to make our evaluation becomes traceable. The least-squares fitting was performed to the logarithms of the cross sections and their rations in the experimental database by using the simultaneous least-squares fitting code SOK. The best precisions of the group-wise cross sections were achieved around 2 to 3 MeV, where the external uncertainties are 1% ($$^{235,238}$$U), 1.5% ($$^{233}$$U, $$^{239}$$Pu) or 2.5% ($$^{241}$$Pu). Well documented experimental fission cross sections are desired for $$^{235}$$U between 100 and 300 keV and $$^{241}$$Pu in the whole energy range since the numbers of the usable experimental datasets are limited and it makes the uncertainties in our evaluation relatively high. The evaluated cross sections were also validated against the spectrum averaged fission cross sections measured under the $$^{252}$$Cf and $$Sigma$$-$$Sigma$$ neutron fields, and we found the newly evaluated cross sections are consistent with the experimental spectrum averaged cross sections well except for $$^{238}$$U fission cross sections measured in the $$^{252}$$Cf neutron fields, which is underestimated by the newly evaluated cross sections as well as those in many other data libraries.

論文

Deuteron and alpha sub-libraries of JENDL-5

中山 梓介; 岩本 修; Sublet, J.-Ch.*

EPJ Web of Conferences, 284, p.14011_1 - 14011_4, 2023/05

日本の評価済み核データライブラリの最新版であるJENDL-5には様々な応用に貢献するために複数のサブライブラリが含まれている。本論文では、主に加速器型中性子源の設計用に開発された重陽子反応サブライブラリと、主にバックエンド分野での使用を目的に開発されたアルファ粒子反応サブライブラリの評価と検証について概説する。重陽子サブライブラリについては、JENDL/DEU-2020の$$^{6,7}$$Li, $$^{9}$$Be, $$^{12,13}$$Cのデータを一部修正し、採用した。加速器構造材料として重要な$$^{27}$$Al, $$^{63,65}$$Cuおよび$$^{93}$$Nbの200MeVまでのデータは、DEURACSコードによる計算をもとに新たに評価した。アルファ粒子サブライブラリについては、LiからSi同位体までの18種類の軽核種について、入射エネルギー15MeVまでのデータをCCONEコードによる計算に基づいて評価した上で、中性子生成断面積のみをJENDL/AN-2005のデータで置き換えた。また、モンテカルロ輸送シミュレーションによる中性子収量に関する検証を両サブライブラリについて実施した。その結果、これらのライブラリに基づくシミュレーションは実験データと良い一致を示すことが確認された。

論文

$$^{241}$$Am neutron capture cross section in the keV region using Si and Fe-filtered neutron beams

Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*

Journal of Nuclear Science and Technology, 60(5), p.489 - 499, 2023/05

 被引用回数:0 パーセンタイル:56.43(Nuclear Science & Technology)

The neutron capture cross-section of $$^{241}$$Am was measured in the keV neutron range using the recently implemented neutron filtering system of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). Filter arrays consisting of 20 cm of $$^{nat}$$Fe and $$^{nat}$$Si were employed in separate measurements to provide filtered neutron beams with averaged neutron energies of 23.5 (Fe), 51.5 and 127.7 (Si) keV. The present $$^{241}$$Am results were obtained relative to the $$^{197}$$Au neutron capture yield by applying the total energy detection principle together with the pulse-height weighting technique. The $$^{241}$$Am neutron capture cross section was determined as 2.72 $$pm$$ 0.29 b at 23.5 keV, 2.14 $$pm$$ 0.26 b at 51.5 keV and 1.32 $$pm$$ 0.10 b at 127.7 keV with total uncertainties in the range of 8 to 12$$%$$, much lower in comparison to the latest time-of-flight experimental data available.

論文

Nuclear many-body effects on particle emission following muon capture on $$^{28}$$Si and $$^{40}$$Ca

湊 太志; 内藤 智也*; 岩本 修

Physical Review C, 107(5), p.054314_1 - 054314_10, 2023/05

 被引用回数:0 パーセンタイル:70.47(Physics, Nuclear)

Muon captures on nuclei have provided us a plenty of knowledge of nuclear properties. Recently, this nature attracts attention again in electronics, because it is argued that charged particle emissions following muon capture on silicon triggers non-negligible soft errors in semiconductors. To investigate the particle emissions from nuclear physics point of view, we develop a new approach using a microscopic model of muon capture and an up-to-date particle emission models. We paid attention to the muon capture rates, the particle emission spectra, and the multiplicities that have a close interrelation with each other, and found that the nuclear many-body correlation including two-particle two-hole excitations is a key to explain them simultaneously.

論文

Evaluation of covariance data in JENDL

岩本 修

EPJ Web of Conferences, 281, p.00009_1 - 00009_4, 2023/03

Evaluation of covariance data for JENDL virtually started after the release of JENDL-3.2. Covariance data were estimated for 16 nuclides in JENDL-3.2 and compiled as JENDL-3.2 Covariance File. For JENDL-4.0, covariance evaluation was much enhanced especially for actinides; the number of nuclides with covariance was 99. With the new evaluations for light nuclides and structure materials, the latest version JENDL-5 provides covariance data for 105 nuclides. The covariances in JENDL were basically evaluated with the least square method with available experimental data. Basic methods were developed at the time of JENDL-3.2 covariance evaluation. While the nuclear reaction modeling codes were changed from the JENDL-3.2 evaluation to the JENDL-4.0 or JENDL-5 evaluations, the covariance evaluation code has been continuously used for all of them. Overview of the covariance evaluation for JENDL will be presented.

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

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

Fast-neutron capture cross section data measurement of minor actinides for development of nuclear transmutation systems

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

EPJ Web of Conferences, 281, p.00014_1 - 00014_4, 2023/03

Long-lived minor actinides (MA) in nuclear waste from nuclear power plants are a long-standing issue to continue nuclear energy production. To solve the issue, researchers have suggested nuclear transmutation, in which long-lived radionuclides are transmuted into stable or shorter-life nuclides via neutron-induced nuclear reactions. Development of nuclear transmutation systems as an accelerator-driven system requires accurate neutron nuclear reaction data. The present research project entitled "Study on accuracy improvement of fast-neutron capture reaction data of long-lived MAs for development of nuclear transmutation systems" have been conducted as a joint collaboration, including Tokyo Tech, Japan Atomic Energy Agency and Kyoto University. This project focuses on the neutron capture reaction of MAs, especially $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$Am, in the fast neutron energy region. The final goal of this project is to improve the accuracies of the neutron capture cross sections of $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$Am employing a high-intensity neutron beam from a spallation source of the Japan Proton Accelerator Research Complex (J-PARC) that reduces uncertainties of measurement. To achieve the goal, a neutron beam filter system in J-PARC, sample characteristic assay, and theoretical reaction model study were developed. In this contribution, the overview and results of the project will be presented.

論文

シグマ委員会60周年にあたって; シグマ委員会60周年に思うこと

岩本 修

核データニュース(インターネット), (134), p.32 - 33, 2023/02

日本原子力学会シグマ委員会の60周年にあたり、JENDLを中心とする核データの研究開発について思うところを述べた。シグマ委員会の歴史は日本の核データ活動の歴史と重なり、その集大成であるJENDLもこの長い活動の結晶と言える。2021年末に公開したJENDL-5はこれまでの知見が集約されると共に、多くのデータに対して最新の測定データやこれまで培われてきた理論的な知見が反映されている。しかしながら、課題も存在し今後も地道な研究開発が必要となる。重要なインフラの一つとしての核データの発展に期待する。

論文

Collaboration with Dr. Efrem Sh. Soukhovitsukii; Our fortuitous experiences on optical model analysis, his contribution to nuclear data activities of Japan and a posthumous study on light-nuclei

国枝 賢; 岩本 修; 深堀 智生; 千葉 敏*

European Physical Journal A, 59(1), p.2_1 - 2_8, 2023/01

 被引用回数:0 パーセンタイル:70.47(Physics, Nuclear)

原子核の変形並びに回転や振動を記述する軟回転体模型を構築し、チャンネル結合法に基づいて核構造の情報を光学模型に取り入れたことは故Soukhovitsukii博士の偉大な成果である。また、博士と原子力機構との共同研究により得られた数々の光学模型解析結果やOPTMANコードは日本の核データライブラリJENDLの開発に多大なる貢献を果たした。本論文では、主に軟回転体模型による核構造解析や光学模型本シャルについての同氏との共同研究成果をレビューする。また、軽原子核に対する原子核の変形と断面積の関係や模型の適用限界など、同氏の没後に得られた新たな解析結果を報告する。

論文

Estimation of double-differential cross-sections of $$^9$$Be(p,xn) reaction for new nuclear data library JENDL-5

国枝 賢; 山本 和喜; 今野 力; 岩元 洋介; 岩本 修; 若林 泰生*; 池田 裕二郎*

Journal of Neutron Research, 24(3-4), p.329 - 335, 2023/01

核データライブラリJENDL-5のために$$^9$$Be(p,xn)反応二重微分断面積の評価を行った。本研究ではまず、理化学研究所で開発された若林関数を内挿法などを工夫してデータベース化し、MCNPやPHITSを用いて薄膜ターゲットに対する検証解析を実施した。それにより、JENDL-4.0/HEや米国のENDF/B-VIII.0と比べて良い予測を与えることを確認した。更に反応断面積の絶対値を若林関数オリジナル値から15%(測定データ間の差異の範囲内で)減少させることにより、更に核データとしての精度が高まることを確認した。以上の知見を投入した新たな核データライブラリJENDL-5を用いることにより、$$^9$$Be(p,xn)反応からの中性子スペクトルや収量を世界一の予測精度で計算することが可能である。

論文

Japanese Evaluated Nuclear Data Library version 5; JENDL-5

岩本 修; 岩本 信之; 国枝 賢; 湊 太志; 中山 梓介; 安部 豊*; 椿原 康介*; 奥村 森*; 石塚 知香子*; 吉田 正*; et al.

Journal of Nuclear Science and Technology, 60(1), p.1 - 60, 2023/01

 被引用回数:17 パーセンタイル:99.99(Nuclear Science & Technology)

The fifth version of Japanese Evaluated Nuclear Data Library, JENDL-5, was developed. JENDL-5 aimed to meet a variety of needs not only from nuclear reactors but also from other applications such as accelerators. Most of the JENDL special purpose files published so far were integrated into JENDL-5 with revisions. JENDL-5 consists of 11 sublibraries: (1) Neutron, (2) Thermal scattering law, (3) Fission product yield, (4) Decay data, (5) Proton, (6) Deuteron, (7) Alpha-particle, (8) Photonuclear, (9) Photo-atomic, (10) Electro-atomic, and (11) Atomic relaxation. The neutron reaction data for a large number of nuclei in JENDL-4.0 were updated ranging from light to heavy ones, including major and minor actinides which affect nuclear reactor calculations. In addition, the number of nuclei of neutron reaction data stored in JENDL-5 was largely increased; the neutron data covered not only all of naturally existing nuclei but also their neighbor ones with half-lives longer than 1 day. JENDL-5 included the originally evaluated data of thermal scattering law and fission product yield for the first time. Light charged-particle and photon induced reaction data were also included for the first time as the JENDL general purpose file.

論文

$$^{241}$$Am neutron capture cross section measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARC

Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*

Journal of Nuclear Science and Technology, 19 Pages, 2023/00

The neutron capture cross-section of $$^{241}$$Am was measured from 10 meV to about 1 MeV using the NaI(Tl) spectrometer of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). The total energy detection principle was applied in conjunction with the pulse-height weighting technique to derive the neutron capture yield. The present cross-section results were normalized using a $$^{197}$$Au sample measurement by applying the saturated resonance method. The thermal cross section was measured to be 708 $$pm$$ 22 b, in agreement within uncertainties to the present evaluation in JENDL-5 of 709 b. Moreover, the results of a shape resonance analysis of the resolved resonance region are also provided in the present dissertation.

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

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

$$^{241}$$Am neutron capture cross section measurement and resonance analysis

Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*

JAEA-Conf 2022-001, p.91 - 96, 2022/11

Neutron capture cross section measurements were performed in 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). The time-of-flight (TOF) methodology was employed in a non-filter condition experiment to determine the neutron capture cross section from thermal to about 100 eV. Moreover, experiments were performed using the neutron filtering system to determine the neutron capture cross section at the energy of 23.5 keV using Fe as filter material. In this study, the preliminary results of the $$^{241}$$Am neutron capture cross section from 10 meV to about 100 eV determined in TOF experiments and at 23.5 keV from Fe filter experiments are presented. In the TOF experiments, the $$^{241}$$Am neutron capture cross section was normalized by means of the saturated resonance method using a Au sample with a mass of 1.5 g. In addition, for the Fe filter experiments, the capture cross section of $$^{241}$$Am at the energy of 23.5 keV was determined relative to the $$^{197}$$Au yield obtained from a measurement using the same Au sample. Moreover, early-stage results of a resonance analysis of the $$^{241}$$Am capture resonances are also presented.

論文

Outline of JENDL-5

岩本 修

JAEA-Conf 2022-001, p.21 - 26, 2022/11

The next version of JENDL general purpose library, JENDL-5, is almost ready to be released. JENDL-5 increases variety and amount of data from the current version JENDL-4.0. Regarding the neutron induced reaction data, which is the most important for reactor applications, the number of the stored nuclides will be around 800, which is almost double of 406 as of JENDL-4.0. They cover not only all stable isotopes but also a large number of unstable isotopes that are much enough for various applications of radiation simulations. The data from light to heavy nuclides have been revised reflecting up-to-date experimental knowledge such as new measurements of cross sections by ANNRI at J-PARC. Fission yield and decay data are also revised with new experimental and theoretical knowledge. New evaluations of thermal scattering law data based on molecular dynamics are adopted for many of materials in JENDL-5 including light and heavy water. The data of other incident particles than neutron that have been developed as special-purpose files are integrated into JENDL-5. For proton, deuteron, alpha-particle and photon induced reactions, the data of JENDL-4.0/HE, JENDL/ImPACT-2018, JENDL/DEU-2020, JENDL/AN-2005, JENDL/PD-2016.1 are adopted. Since JENDL/AN-2005 contains only neutron-emission related data, date needed for radiation transportation codes are complemented. Regarding neutron induced reaction, the data of high energy reaction above 20 MeV and activation cross section are also integrated from JENDL-4.0/HE, JENDL/ImPACT-2018 and JENDL/AD-2017.

報告書

EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5; Inputs and outputs

大塚 直彦*; 岩本 修

JAEA-Data/Code 2022-005, 102 Pages, 2022/10

JAEA-Data-Code-2022-005.pdf:2.18MB
JAEA-Data-Code-2022-005-appendix(CD-ROM).zip:3.85MB

$$^{233,235}$$Uと$$^{239,241}$$Puの10keVから200MeVの中性子入射核分裂断面積、および$$^{238}$$Uと$$^{240}$$Puの100keVから200MeVまでの中性子入射核反応断面積をJENDL-5のために同時評価した。実験断面積とその比の対数をシュミットロスの屋根関数(Schmittroth's roof function)の線形結合で表現し、その係数を最小二乗法により決定した。同時評価コードSOKを規格化が任意の実験値に拡張したものを本評価に用いた。本報告書は(1)実験データベースの構築、(2)ドレスデン工科大学(TUD)・ラジウム研究所(KRI)の共同測定で得られたデータの選定、(3)本評価で得られた断面積の最近の主なライブラリとの比較、(4)1970年代に測定された235Uデータの影響、について述べる。

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