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論文

MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 3

佐藤 一憲; 吉川 信治; 山下 拓哉; 下村 健太; Cibula, M.*; 溝上 伸也*

Nuclear Engineering and Design, 422, p.113088_1 - 113088_24, 2024/06

The accident progression of the in-vessel phase of Fukushima Daiichi Nuclear Power Station Unit 1 was analyzed using the MAAP code. Although there is a large uncertainty in the initial stage of accident progression behavior in Unit 1 with little measurement data, it is presumed to have similarities to that of Unit 3. As a result, in Unit 1, since there was almost no alternative water injection during the in-vessel phase, cooling of the debris transferred to the lower plenum was small. It was likely that a large molten pool of metals had formed, and that the steam supply to the high-temperature core materials was suppressed and metal oxidation was relatively small. The analysis results for Unit 1 were compared with those for Units 2 and 3, and differences between units such as the thermal conditions of the debris that relocated to the pedestal and the degree of metal oxidation were shown.

論文

Changes in molecular conformation and electronic structure of DNA under $$^{12}$$C ions based on first-principles calculations

関川 卓也; 松谷 悠佑; Hwang, B.*; 石坂 優人*; 川井 弘之*; 大野 義章*; 佐藤 達彦; 甲斐 健師

Nuclear Instruments and Methods in Physics Research B, 548, p.165231_1 - 165231_6, 2024/03

 被引用回数:0 パーセンタイル:0.44(Instruments & Instrumentation)

放射線の人体に与える影響の主な原因として、遺伝情報を担うDNAの損傷が考えられている。しかし、DNAが放射線損傷によりどのような分子構造変化を示すかは十分理解されていない。DNAに放射線を照射すると様々な種類のDNA損傷が形成されることが報告されていることから、我々のグループではDNAが受ける損傷と放射線によって引き起こされる様々なパターンのイオン化の関係を調べてきた。これまでDNAを模した剛体モデルを用いた簡易な体系における解析を行っていたが、人体への影響を考える上で重要と考えられるDNAの分子構造変化を解析するためにはより詳細な計算を必要とする。そこで、本研究では分子構造に基づいて電子状態を議論できる第一原理計算ソフトウェアOpenMXを用いてDNAの分子構造変化を明らかにすることを試みた。具体的には、放射線により1電子及び2電子が電離した状況のDNAを仮定し、最安定構造、バンド分散、及び波動関数を計算した。発表では、粒子・重イオン輸送計算コードPHITSを用いて計算した放射線の線種及びエネルギーとDNAの分子構造変化の関係とともに議論する。また、放射線物理・固体物理の双方の観点から、放射線がもたらすDNAの基礎物性変化(DNA損傷の最初期過程に相当)について議論する。

論文

MAAP code analysis focusing on the fuel debris conditions in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 3

佐藤 一憲; 吉川 信治; 山下 拓哉; 下村 健太; Cibula, M.*; 溝上 伸也*

Nuclear Engineering and Design, 414, p.112574_1 - 112574_20, 2023/12

Based on the updated knowledge from plant-internal investigations, experiments and computer-model simulations until now, the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 3 was analyzed using the MAAP code. In Unit 3, it is considered that ca. 40 percent of UO$$_{2}$$ fuel was molten when core materials relocated to the lower plenum of the reactor pressure vessel. Initially relocated molten materials would have been fragmented by mixing with liquid water, while solid materials would have relocated later on. With this two-step relocation, debris in the lower plenum seems to have been permeable for coolant, thus debris seems to have been once cooled down effectively. Although the present MAAP analysis seems to slightly underestimate core-material oxidation during the relocation period, this probable underestimation was compensated for by an existing study that was considered more reliable, so that more realistic debris conditions in the lower plenum could be obtained. Probable debris reheat-up behavior was evaluated based on interpretation of the pressure data. This evaluation predicted that the fuel debris in the lower plenum was basically in solid-phase at the time when it relocated to the pedestal. With this study, basic validity of the former prediction of the Unit 3 accident progression behavior was confirmed, and detailed boundary conditions for future studies addressing the later phases were provided.

論文

Comprehensive analysis and evaluation of Fukushima Daiichi Nuclear Power Station Unit 3

山下 拓哉; 本多 剛*; 溝上 暢人*; 野崎 謙一朗*; 鈴木 博之*; Pellegrini, M.*; 酒井 健*; 佐藤 一憲; 溝上 伸也*

Nuclear Technology, 209(6), p.902 - 927, 2023/06

 被引用回数:2 パーセンタイル:90.12(Nuclear Science & Technology)

The estimation and understanding of the state of fuel debris and fission products inside the plant is an essential step in the decommissioning of the TEPCO Fukushima Daiichi Nuclear Power Station (1F). However, the direct observation of the plant interior, which is under a high radiation environment, is difficult and limited. Therefore, in order to understand the plant interior conditions, a comprehensive analysis and evaluation is necessary, based on various measurement data from the plant, analysis of plant data during the accident progression phase and information obtained from computer simulations for this phase. These evaluations can be used to estimate the conditions of the interior of the reactor pressure vessel (RPV) and the primary containment vessel (PCV). Herein, 1F Unit 3 was addressed as the subject to produce an estimated diagram of the fuel debris distribution from data obtained about the RPV and PCV based on the comprehensive evaluation of various measurement data and information obtained from the accident progression analysis, which were released to the public in November 2022.

論文

MAAP code analysis focusing on the fuel debris condition in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 2

佐藤 一憲; 吉川 信治; 山下 拓哉; Cibula, M.*; 溝上 伸也*

Nuclear Engineering and Design, 404, p.112205_1 - 112205_21, 2023/04

 被引用回数:2 パーセンタイル:90.12(Nuclear Science & Technology)

これまでのプラント内部調査、実験、コンピュータモデルシミュレーションから得られた最新の知見に基づき、福島第一原子力発電所2号機の原子炉圧力炉容器内フェーズに対するMAAP解析を実施した。2号機では、炉心物質が圧力容器の下部プレナムに移動し、そこで冷却材によって冷却されて固化したときのエンタルピーが比較的低かったと考えられる。MAAPコードは、炉心物質リロケーション期間中の炉心物質の酸化の程度を過小評価する傾向があるが、酸化に係るより信頼性の高い既存研究を活用することによって補正を行うことで、下部プレナム内の燃料デブリ状態の、より現実的な評価を行った。この評価により、2号機事故進展挙動に係る既往予測の基本的妥当性が確認され、今後の後続過程研究を進めるための詳細な境界条件を提供した。下部ヘッドの破損とペデスタルへのデブリ移行に至るデブリ再昇温プロセスに対処する将来研究に、本研究で得た境界条件を反映する必要がある。

論文

The Experimental and simulation results of LIVE-J2 test; Investigation on heat transfer in a solid-liquid mixture pool

間所 寛; 山下 拓哉; Gaus-Liu, X.*; Cron, T.*; Fluhrer, B.*; 佐藤 一憲; 溝上 伸也*

Nuclear Technology, 209(2), p.144 - 168, 2023/02

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

Since the reactor pressure vessel (RPV) lower head failure determines the subsequent ex-vessel accident progression, it is a key issue to understand the accident progression of Fukushima Daiichi Nuclear Power Station (1F). The RPV failure is largely affected by thermal loads on the vessel wall and thus it is inevitable to understand thermal behavior of molten metallic pool with co- existence of solid oxide fuel debris. In the past decades, numerous experiments have been conducted to investigate a homogeneous molten pool behavior. Few experiments, however, addresses the melting and heat transfer process of debris bed consisted of materials with different melting temperatures. LIVE-J2 experiment aimed to provide the experimental data on a solid-liquid mixture pool in a simulated RPV lower head under various conditions. The extensive measurements of the melt temperature indicate the heat transfer regimes in a solid-liquid mixture pool. The test results showed that the conductive heat transfer was dominant during the steady state along the vessel wall boundary and that convective heat transfer takes place inside the mixture pool. Besides the experimental performance, the test case was numerically simulated by using ANSYS Fluent. The simulation results generally agree with the measured experimental data. The flow regime and transient melt evolution were able to be estimated by the calculated velocity field and the crust thickness, respectively.

論文

Recent improvements of the Particle and Heavy Ion Transport code System; PHITS version 3.33

佐藤 達彦; 岩元 洋介; 橋本 慎太郎; 小川 達彦; 古田 琢哉; 安部 晋一郎; 甲斐 健師; 松谷 悠佑; 松田 規宏; 平田 悠歩; et al.

Journal of Nuclear Science and Technology, 9 Pages, 2023/00

 被引用回数:5 パーセンタイル:98.08(Nuclear Science & Technology)

放射線挙動解析コードPHITSは、モンテカルロ法に基づいてほぼ全ての放射線の挙動を解析することができる。その最新版であるPHITS version 3.31を開発し公開した。最新版では、高エネルギー核データに対する親和性や飛跡構造解析アルゴリズムなどが改良されている。また、PHIG-3DやRT-PHITSなど、パッケージに組み込まれた外部ソフトウェアも充実している。本論文では、2017年にリリースされたPHITS3.02以降に導入された新しい機能について説明する。

論文

Measurement of differential cross sections for $$Sigma^+ p$$ elastic scattering in the momentum range 0.44-0.80 GeV/c

七村 拓野; 藤田 真奈美; 長谷川 勝一; 市川 真也; 市川 裕大; 今井 憲一*; 成木 恵; 佐藤 進; 佐甲 博之; 田村 裕和; et al.

Progress of Theoretical and Experimental Physics (Internet), 2022(9), p.093D01_1 - 093D01_35, 2022/09

 被引用回数:5 パーセンタイル:67.44(Physics, Multidisciplinary)

We performed a novel $$Sigma^+p$$ scattering experiment at the J-PARC Hadron Experimental Facility. Approximately 2400 $$Sigma^+p$$ elastic scattering events were identified from $$4.9 times 10^7$$ tagged $$Sigma^+$$ particles in the $$Sigma^+$$ momentum range 0.44 - 0.80 GeV/c. The differential cross sections of the $$Sigma^+p$$ elastic scattering were derived with much better precision than in previous experiments. The obtained differential cross sections were approximately 2 mb/sr or less, which were not as large as those predicted by the fss2 and FSS models based on the quark cluster model in the short-range region. By performing phase-shift analyses for the obtained differential cross sections, we experimentally derived the phase shifts of the $$^3S_1$$ and $$^1P_1$$ channels for the first time. The phase shift of the 3S1 channel, where a large repulsive core was predicted owing to the Pauli effect between quarks, was evaluated to be $$20^circ<|delta_{^3S_1}|<35^circ$$. If the sign of $$delta_{^3S_1}$$ is assumed to be negative, the interaction in this channel is moderately repulsive, as the Nijmegen extended-sort-core models predicted.

論文

BWR lower head penetration failure test focusing on eutectic melting

山下 拓哉; 佐藤 拓未; 間所 寛; 永江 勇二

Annals of Nuclear Energy, 173, p.109129_1 - 109129_15, 2022/08

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

Decommissioning work occasioned by the Fukushima Daiichi Nuclear Power Station (1F) accident of March 2011 is in progress. Severe accident (SA) analysis, testing, and internal investigation are being used to grasp the 1F internal state. A PWR system that refers to the TMI-2 accident is typical for SA codes and testing, on the other hand, a BWR system like 1F is uncommon, understanding the 1F internal state is challenging. The present study conducted the ELSA-1 test, a test that focused on damage from eutectic melting of the liquid metal pool and control rod drive (CRD), to elucidate the lower head (LH) failure mechanism in the 1F accident. The results demonstrated that depending on the condition of the melt pool formed in the lower plenum, a factor of LH boundary failure was due to eutectic melting. In addition, the state related to the CRD structure of 1F unit 2 were estimated.

論文

Development of the DICOM-based Monte Carlo dose reconstruction system for a retrospective study on the secondary cancer risk in carbon ion radiotherapy

古田 琢哉; 古場 裕介*; 橋本 慎太郎; Chang, W.*; 米内 俊祐*; 松本 真之介*; 石川 諒尚*; 佐藤 達彦

Physics in Medicine & Biology, 67(14), p.145002_1 - 145002_15, 2022/07

 被引用回数:2 パーセンタイル:47.19(Engineering, Biomedical)

炭素線治療は従来の放射線治療よりも腫瘍部への線量集中性に関する優位性を持つが、二次的ながんの発生原因となり得る正常組織への照射を完全に無くすことは困難である。そのため、発がんリスクを照射炭素ビームの核反応によって生成される二次粒子による線量まで含めて評価するには、計算シミュレーション解析が有効となる。本研究では、PHITSコードを中核とした炭素線治療の線量再構築システムを開発した。このシステムでは、治療計画を記録したDICOMデータから自動でPHITSの入力ファイルを作成し、PHITSシミュレーションの実行によって腫瘍および周辺正常組織での線量分布を計算する。PHITSの様々な機能を利用することで、粒子毎の線量寄与や二次粒子の発生場所の特定など、詳細な解析が実施可能である。開発したシステムの妥当性は、水中での線量分布の実験結果や人体等価ファントムへの治療計画との比較により確認した。今後、本システムは量子科学技術研究開発機構において、過去の治療データを用いたシミュレーション解析による遡及的研究に利用される予定である。

論文

Development plan of failure mitigation technologies for improving resilience of nuclear structures

笠原 直人*; 山野 秀将; 中村 いずみ*; 出町 和之*; 佐藤 拓哉*; 一宮 正和*

Transactions of 26th International Conference on Structural Mechanics in Reactor Technology (SMiRT-26) (Internet), 8 Pages, 2022/07

破壊制御を利用して、設計想定を超える事象によって破損が生じた場合に、その拡大を抑制する技術の開発を進めている。開発課題として、(1)超高温時の破損拡大抑制技術、(2)課題地震時の破損拡大抑制技術、(3)原子炉構造レジリエンス向上手法の3つの計画を立てた。

論文

Post-test analyses of the CMMR-4 test

山下 拓哉; 間所 寛; 佐藤 一憲

Journal of Nuclear Engineering and Radiation Science, 8(2), p.021701_1 - 021701_13, 2022/04

Understanding the final distribution of core materials and their characteristics is important for decommissioning the Fukushima Daiichi Nuclear Power Station (1F). Such characteristics depend on the accident progression in each unit. However, boiling water reactor accident progression involves great uncertainty. This uncertainty, which was clarified by MAAP-MELCOR Crosswalk, cannot be resolved with existing knowledge and was thus addressed in this work through core material melting and relocation (CMMR) tests. For the test bundle, ZrO$$_{2}$$ pellets were installed instead of UO$$_{2}$$ pellets. A plasma heating system was used for the tests. In the CMMR-4 test, useful information was obtained on the core state just before slumping. The presence of macroscopic gas permeability of the core approaching ceramic fuel melting was confirmed, and the fuel columns remained standing, suggesting that the collapse of fuel columns, which is likely in the reactor condition, would not allow effective relocation of the hottest fuel away from the bottom of the core. This information will help us comprehend core degradation in boiling water reactors, similar to those in 1F. In addition, useful information on abrasive water suspension jet (AWSJ) cutting for debris-containing boride was obtained in the process of dismantling the test bundle. When the mixing debris that contains oxide, metal, and boride material is cut, AWSJ may be repelled by the boride in the debris, which may cut unexpected parts, thus generating a large amount of waste in cutting the boride part in the targeted debris. This information will help the decommissioning of 1F.

論文

プルトニウムの体外排出に向けたキレート剤による除染に関する基礎検討; X線吸収分光法によるプルトニウム模擬元素とキレート剤との結合性評価

上原 章寛*; Shuhui, X.*; 佐藤 遼太朗*; 松村 大樹; 辻 卓也; 薬丸 晴子*; 城 鮎美*; 齋藤 寛之*; 田中 泉*; 石原 弘*; et al.

X線分析の進歩,53, p.223 - 229, 2022/03

体内にアクチニドなどの放射性物質が取り込まれると、生体内配位子がアクチニドと化合物を生成し、体内滞留の原因となりうる。本研究では、アクチニドを体外に排出させるためのキレート剤の結合性評価を行うため、キレート剤と結合した元素の局所構造をX線吸収分光法によって解析し結合力を評価した。プルトニウム模擬元素としてジルコニウム(Zr),キレート剤として、EHBP(1-hydroxyethylidene-1,1-diphosphonate)およびDTPA (diethylenetriaminepentaacetate)を用いた。ZrはEHBPと八面体構造の錯体を形成するとともに、Zr-EHBP錯体はZr-DTPA錯体より強い結合を有することが分かった。これらの知見は、放射性元素による内部被ばく線量評価や、放射性元素を体外に取り除くための適切な除染方法の提案につながる。

論文

LIVE-J1 experiment on debris melting behavior toward understanding late in-vessel accident progression of the Fukushima Daiichi Nuclear Power Station

間所 寛; 山下 拓哉; 佐藤 一憲; Gaus-Liu, X.*; Cron, T.*; Fluhrer, B.*; St$"a$ngle, R.*; Wenz, T.*; Vervoortz, M.*; 溝上 伸也

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03

Debris and molten pool behavior in the reactor pressure vessel (RPV) lower plenum is a key factor to determine its failure mode, which affects the initial condition of ex-vessel accident progression and the debris characteristics. These are necessary information to accomplish safe decommissioning of the Fukushima Daiichi Nuclear Power Station. After dryout of the solidified debris in the lower plenum, metallic debris is expected to melt prior to the oxide debris due to its lower melting temperature. The lower head failure is likely be originated by the local thermal load attack of a melting debris bed. Numerous experiments have been conducted in the past decades to investigate the homogeneous molten pool behavior with external cooling. However, few experiments address the transient heat transfer of solid-liquid mixture without external cooling. In order to enrich the experimental database of melting and heat transfer process of debris bed consisted of materials with different melting temperatures, LIVE-J1 experiment was conducted using ceramic and nitrate particles as high melting and low melting temperature simulant materials, respectively. The test results showed that debris height decreased gradually as the nitrate particles melt, and molten zone and thermal load on vessel wall were shifted from bottom upwards. Both conductive and convective heat transfer could take place in a solid-liquid mixture pool. These results can support the information from the internal investigations of the primary containment vessel and deepen the understanding of the accident progression.

論文

Space weather benchmarks on Japanese society

石井 守*; 塩田 大幸*; 垰 千尋*; 海老原 祐輔*; 藤原 均*; 石井 貴子*; 一本 潔*; 片岡 龍峰*; 古賀 清一*; 久保 勇樹*; et al.

Earth, Planets and Space (Internet), 73(1), p.108_1 - 108_20, 2021/12

 被引用回数:8 パーセンタイル:57.39(Geosciences, Multidisciplinary)

科研費新学術領域研究・太陽地球圏環境予測(PSTEP)の一環として、日本における宇宙天気災害の発生規模と頻度の関係を包括的に調査した。調査した情報は、国内における宇宙天気ユーザーが理解できる形で公開した。本論文では、その包括的調査の結果をまとめるとともに、宇宙天気災害が電力や航空業界に与える経済的損失に関して定量評価した結果も紹介する。

論文

Measurement of the differential cross sections of the $$Sigma^- p$$ elastic scattering in momentum range 470 to 850 MeV/$$c$$

三輪 浩司*; 藤田 真奈美; 長谷川 勝一; 細見 健二; 市川 裕大; 今井 憲一*; 七村 拓野; 成木 恵; 佐甲 博之; 佐藤 進; et al.

Physical Review C, 104(4), p.045204_1 - 045204_20, 2021/10

 被引用回数:12 パーセンタイル:89.15(Physics, Nuclear)

A high statistics $$Sigma p$$ scattering experiment is performed at the J-PARC Hadron Experimental Facility. Momentum-tagged $$Sigma^-$$s running in a liquid hydrogen target are accumulated by detecting the reaction with a high intensity $$pi^-$$ beam of 20 M/spill. The differential cross sections of the $$Sigma^- p$$ elastic scattering were derived with a drastically improved accuracy by identifying approximately 4,500 events from 1.72 $$times$$ 10$$^7$$ $$Sigma^-$$. The derived differential cross section shows a clear forward-peaking angular distribution for a $$Sigma^-$$ momentum range from 470 to 850 MeV/$$c$$. The accurate data will impose a strong constraint on the theoretical models of the baryon-baryon interactions.

論文

Technical Note: Validation of a material assignment method for a retrospective study of carbon-ion radiotherapy using Monte Carlo simulation

Chang, W.*; 古場 裕介*; 古田 琢哉; 米内 俊祐*; 橋本 慎太郎; 松本 真之介*; 佐藤 達彦

Journal of Radiation Research (Internet), 62(5), p.846 - 855, 2021/09

 被引用回数:2 パーセンタイル:26.61(Biology)

炭素線治療の治療計画をモンテカルロシミュレーションによって再評価するためのツール開発の一環として二つの重要な手法を考案した。一つは治療計画装置に含まれる校正済みのCT-水阻止能表を反映しつつ、患者CT画像から物質識別を行う手法である。もう一つの手法は、粒子およびエネルギー毎に生体物質と水との阻止能比を考慮し、水等価線量を導出することを目的としたものである。これらの手法の有効性を確認するため、生体物質および水で構成される均質および不均質ファントムに対し、SOBPサイズ8cmの炭素線を400MeV/uで照射するシミュレーションをPHITSで計算し、得られた線量深さ分布を従来の治療計画装置による結果と比較した。その結果、従来の治療計画装置で採用されている生体物質を全て水に置換する手法では、異なる物質において二次粒子の発生率が一次粒子の阻止能に単純に比例するため、二次粒子による線量寄与を評価する上で不適切であることが分かった。一方、各物質の二次粒子の発生率を適切に考慮した新しい手法は炭素線治療の再評価において、重要な役割を果たすことが期待できることが分かった。

論文

Medical application of Particle and Heavy Ion Transport code System PHITS

古田 琢哉; 佐藤 達彦

Radiological Physics and Technology, 14(3), p.215 - 225, 2021/09

PHITSユーザー数は、集計を開始した2010年以降に順調な増加傾向を示している。その中で、近年は医学物理分野における新規ユーザー数の増加が顕著となっている。そのため、PHITSを利用した数多くの研究が発表されており、その内容も放射線治療応用、施設の遮蔽計算、放射線生物学応用、医療機器研究開発等、多岐に渡っている。本稿では、これら応用研究の具体例を示しつつレビューを行うとともに、医学物理応用研究で有益なPHITSの機能を紹介する。

論文

First observation of a nuclear $$s$$-state of a $$Xi$$ hypernucleus, $$^{15}_{Xi}{rm C}$$

吉本 雅浩*; 藤田 真奈美; 橋本 直; 早川 修平; 市川 裕大; 市川 真也; 今井 憲一*; 七村 拓野; 成木 恵; 佐甲 博之; et al.

Progress of Theoretical and Experimental Physics (Internet), 2021(7), p.073D02_1 - 073D02_19, 2021/07

 被引用回数:13 パーセンタイル:81.3(Physics, Multidisciplinary)

Bound-systems of $$Xi^-$$-$$^{14}_{}{rm N}$$ are studied via $$Xi^-$$ capture at rest followed by emission of a twin single-$$Lambda$$ hypernucleus in the emulsion detectors. Two events forming extremely deep $$Xi^-$$ bound states were obtained by analysis of a hybrid method in the E07 experiment at J-PARC and reanalysis of the E373 experiment at KEK-PS. The decay mode of one event was assigned as $$Xi^-+^{14}_{}{rm N}to^{5}_{Lambda}{rm He}$$+$$^{5}_{Lambda}{rm He}$$+$$^{4}_{}{rm He}$$+$$n$$. Since there are no excited states for daughter particles, the binding energy of the $$Xi^-$$ hyperon, $$B_{Xi^-}$$, in $$^{14}_{}{rm N}$$ nucleus was uniquely determined to be 6.27 $$pm$$ 0.27 MeV. Another $$Xi^-$$-$$^{14}_{}{rm N}$$ system via the decay $$^{9}_{Lambda}{rm Be}$$ + $$^{5}_{Lambda}{rm He}$$ + $$n$$ brings a $$B_{Xi^-}$$ value, 8.00 $$pm$$ 0.77 MeV or 4.96 $$pm$$ 0.77 MeV, where the two possible values of $$B_{Xi^-}$$ correspond to the ground and the excited states of the daughter $$^{9}_{Lambda}{rm Be}$$ nucleus, respectively. Because the $$B_{Xi^-}$$ values are larger than those of the previously reported events (KISO and IBUKI), which are both interpreted as the nuclear $$1p$$ state of the $$Xi^-$$-$$^{14}_{}{rm N}$$ system, these new events give the first indication of the nuclear $$1s$$ state of the $$Xi$$ hypernucleus, $$^{15}_{Xi}{rm C}$$.

論文

J-PARC E07; Systematic study of double strangeness system with hybrid emulsion method

吉田 純也; 赤石 貴也; 藤田 真奈美; 長谷川 勝一; 橋本 直; 細見 健二; 市川 真也; 市川 裕大; 今井 憲一*; Kim, S.; et al.

JPS Conference Proceedings (Internet), 33, p.011112_1 - 011112_8, 2021/03

J-PARC E07 is the most ambitious and complex emulsion experiment to date investigating double hypernuclei with Hybrid emulsion method. The physics run at the K1.8 beam line in the J-PARC hadron experimental facility have been completed in 2017. The emulsion sheets are presently being analyzed with dedicated optical microscopes. Current statistics are estimated to be more 3 times than that of previous experiments. Quantitative data on the $$Lambda Lambda$$ and $$Xi N$$ interaction are being accumulated successfully via analysis of double $$Lambda$$ and $$Xi$$ hypernuclei. Multiple $$Xi$$ hypernucleus candidates suggests several features about $$Xi$$ hypernucleus that the identification efficiency of $$^{15}_Xi$$C is significantly higher than other mode, many daughters of $$^{15}_Xi$$C are identified as He or Be, and multiple bound states of $$Xi^-$$ exist in the $$^{14}$$N nucleus. An analysis of X-ray spectroscopy of $$Xi^-$$ hyperatoms are ongoing.

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