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Porcheron, E.*; Leblois, Y.*; Journeau, C.*; Delacroix, J.*; Molina, D.*; Suteau, C.*; Berlemont, R.*; Bouland, A.*; Lallot, Y.*; Roulet, D.*; et al.
Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR2022) (Internet), 5 Pages, 2022/10
福島第一原子力発電所(1F)の事故炉廃止措置における重要な課題の一つが、燃料デブリの取り出しである。ONET Technologies, CEA, IRSNからなるフランスのコンソーシアムがJAEA/CLADSのために実施したURASOLプロジェクトは、燃料デブリ模擬物質の熱的・機械的加工による放射性エアロゾルの生成と特性に関する科学的基礎データの取得に取り組んでいる。VITAE施設で行われる加熱試験はレーザーによる熱的切断の代表的な条件を模擬している。機械的切断では、FUJISAN施設においてコアボーリング試験を実施した。燃料デブリ模擬物質は、非放射性試験と放射性試験のために開発されている。化学的特性評価と粒径情報の取得は、デブリ取り出しで発生する可能性のある放射性粒子の特性推定のために実施された。これらの情報は1Fにおける燃料デブリ取り出し作業において放射線防護上の対策を評価するうえで重要な情報である。
Journeau, C.*; Molina, D.*; Brackx, E.*; Berlemont, R.*; 坪田 陽一
Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR2022) (Internet), 5 Pages, 2022/10
CEAは、劣化ウランを使用したUO
またはHfOを(核燃料としての)UOの 代替として用いて、福島第一原子力発電所の模擬燃料デブリを製造した。溶融燃料-コンクリート相互作用によって生じたEx-vessel模擬燃料デブリでは、酸化物相の密度が金属相の密度より軽くなる。それゆえ重い金属質の相が底に偏析する。このうち3つの金属質試料を、CEAカダラッシュ研究所でのハンドソー切断、及び同研究所のFUJISAN施設でコアボーリング装置により機械的に切断された。これらの金属ブロックのうち、2つは非常に切断しにくく(1つはUO試料、もう1つはHfO試料)、最後の1つはより簡単に切断可能であった。これらの3つの金属ブロックの金相分析(SEM-EDSとXRD)の類似点/相違点に関して議論する予定である。この経験は、福島第一原子力発電所の燃料デブリの切断・回収を視野に入れた場合、有益な学びとなる。
垣内 一雄; 山内 紹裕*; 天谷 政樹; 宇田川 豊; 北野 剛司*
Proceedings of TopFuel 2022 (Internet), p.409 - 418, 2022/10
In order to examine the influence of cladding microstructural changes upon the mechanical property of the fuel cladding under LOCA conditions in a more direct and quantitative manner, the nanoindentation method has been applied to Zircaloy-4 cladding specimens after LOCA simulated tests (about 1473 K, ECR 20%, quench at 973 K after slow cooling); results for two specimens taken from the rupture opening part and secondary hydriding part were compared. In addition to hardness and Young's modulus, the plastic work fraction that corresponds to the relative ductility was evaluated from the load-displacement curve. The plastic work fraction at the secondary hydriding part was found to be obviously lower than that at the rupture opening part and closer to that in 
-Zr(O) layers beneath the outer surface. This result from the nanoindentation method agrees with the conventional knowledge about low ductility at the secondary hydriding part.
Guglielmi, Y.*; 青木 和弘; Cook, P.*; Soom, F.*; Cappa, F.*; 田中 遊雲
Tectonophysics, 819, p.229084_1 - 229084_22, 2021/11
被引用回数：1 パーセンタイル：10.87(Geochemistry & Geophysics)2011年Mw6.7の福島県浜通り地震に伴う地表断層の再活性化メカニズムについて、ボーリング孔への注水試験を実施し、検討した。本研究では、断層のリアクティベーションのために、2つの断層区間を選択した。1つは地震時に地表変位が現れた塩ノ平サイト、もう1つは地震時に変位しなかった区間である水上北サイトである。断層の上下を密閉したボーリング孔に注水を行うことで、断層を固定している断層面の有効応力を段階的に減少させ、断層を破壊させる。この断層が破壊している間に、ボーリング孔の変位,流体圧,注入流量を連続的にモニターした。取得したデータを水理-力学連成モデルを用いて解析し、断層の再活性化モードを検討した。その結果、塩ノ平サイトでは、純粋なダイラタントスリップ応答を示したが、水上北サイトでは、断層の高い摩擦強度、粘着力に関連した複雑な応答を示した。また、塩ノ平サイトのすべりの解析から、塩ノ平断層の摩擦がすべり速度に基づくクーロン破壊として合理的にモデル化され、室内試験で求めた摩擦係数と整合的であった。本研究では、同一断層系の2つのセグメント間で、断層の物理的性質や破断メカニズムに大きな違いがあることを明らかにし、大規模地震時の地表破断の影響等の地震ハザードをより適切に評価するための展望を開くことができた。
Soba, A.*; Prudil, A.*; Zhang, J.*; Dethioux, A.*; Han, Z.*; Dostal, M.*; Matocha, V.*; Marelle, V.*; Lasnel-Payan, J.*; Kulacsy, K.*; et al.
Proceedings of TopFuel 2021 (Internet), 10 Pages, 2021/10
The NEA Expert Group on Reactor Fuel Performance (EGRFP) proposed a benchmark on fuel performance codes modeling of pellet-cladding mechanical interation (PCMI). The aim of the benchmark was to improve understanding and modeling of PCMI amongst NEA member organizations. This was achieved by comparing PCMI predictions for a number of specified cases. The results of the two hypothetical cases (1 and 2) were presented earlier. The two final cases (3 and 4) are comparison between calculations and measurements, which will be published as NEA reports. This paper focuses on Case 3, which consists of eight beginning of life (BOL) sub-cases (3a to 3h) each with different pellet designs that have undergone ramping in the Halden Reactor. The aforementioned experiments are known as the IFA-118 experiments and were performed from 1969 to 1970. The variations between cases include four different pellets dimensions (7, 14, 20 and 30 mm of height), two different gapsizes between pellet-cladding (40 and 100 microns) and three variations on pellet face geometry (flat, dishing and dishing with chamfer). Such diversity has allowed exploring the codes sensitivity to these individual factors.
Zhou, Q.*; 斉藤 拓巳*; 鈴木 誠矢; 矢野 公彦; 鈴木 俊一*
Journal of Nuclear Science and Technology, 58(4), p.461 - 472, 2021/04
被引用回数：6 パーセンタイル：65.59(Nuclear Science & Technology)During the decommissioning of Fukushima Daiichi Nuclear Power Plant, the dismantling of massive fuel debris is important for the defueling process. The production and dispersion of radioactive microparticles highly depends on the cutting technique implemented. Previous studies have been conducted on the development of cutting techniques and the treatment of radioactive particles generation during the cutting process. Besides, adequate understanding of the microparticle products during the cuttings of fuel debris is of vital necessity. Nowadays, geopolymer application is proposed as a covering material during the fuel debris retrieval in order to keep the structural integrity of damaged components. In this study, the microparticle products during mechanical and laser cutting of fuel debris simulants (Hafnium oxide and Tungsten(IV) oxide pellets) and geopolymer material were investigated. The cuttings have been carried out for samples of the simulants, geopolymer, and simulants with geopolymer covering. The generated particles were collected and investigated by laser diffraction particle size analyzer and Scanning Electron Microscope with X-ray spectrometry. Particles with diverse sizes and morphologies were observed from the products of each sample. It also appears that particles with unique sizes and morphologies can generate from the laser cuttings due to the thermal effect of laser cutting.
Li, F.; 三原 武; 宇田川 豊; 天谷 政樹
Journal of Nuclear Science and Technology, 57(6), p.633 - 645, 2020/06
被引用回数：3 パーセンタイル：24.28(Nuclear Science & Technology)To better understand the failure limit of fuel cladding during the pellet-cladding mechanical interaction (PCMI) phase of a reactivity-initiated accident (RIA), pre-cracked and hydrided cladding samples with base metal final heat-treatment status of cold worked (CW) and recrystallized (RX) were tested under biaxial stress conditions (axial to hoop strain ratios of 0 and 0.5). Displacement-controlled biaxial-expansion-due-to-compression (biaxial-EDC) tests were performed to obtain the hoop strain at failure (failure strain) of the samples. The conversion of the failure strains to J-integral at failure by finite-element analysis involving data of stress-relieved (SR) cladding specimens from our previous study revealed that the failure limit in the dimension of J-integral at failure unifies the effects of pre-crack depth. About 30 to 50 percent reduction in the J-integral at failure was observed as the strain ratio increased from 0 to 0.5 irrespective of the annealing type, pre-crack depth, and hydrogen content. the rate of fractional decreases of J-integral at failure with increase of hydrogen content are in the order of CW
SRRX, which are essentially independent of strain ratio for the CW and SR samples. The results were incorporated into the failure prediction model of the JAEA's fuel performance code in the form of a correction factor that considers the biaxial loading effect.
谷口 良徳; 宇田川 豊; 天谷 政樹
Annals of Nuclear Energy, 139, p.107188_1 - 107188_7, 2020/05
被引用回数：1 パーセンタイル：12.16(Nuclear Science & Technology)The fuel-failure-limit data obtained in the simulated reactivity-initiated-accident experiment SPERT-CDC 859 (SPERT859) has entailed a lot of discussions if it represents fuel-failure behavior of typical commercial LWRs for its specific pre-irradiation condition and fuel state. The fuel-rod conditions before and during SPERT859 were thus assessed by the fuel-performance codes FEMAXI-8 and RANNS with focusing on cladding corrosion and its effect on the failure limit of the test rod. The analysis showed that the fuel cladding was probably excessively corroded even when the influential calculation conditions such as fuel swelling and creep models were determined so that the lowest limit of the cladding oxide layer thickness was captured. Such assumption of excessive cladding corrosion during pre-irradiation well explains not only the test-rod state before pulse irradiation but also the fuel-failure limit observed. Such understanding undermines anew the representativeness of the test data as a direct basis of safety evaluation for LWR fuels.
and chromia-alumina additive fuels under simulated reactivity-initiated accidents; A Comparative analysis with FEMAXI-8宇田川 豊; 三原 武; 谷口 良徳; 垣内 一雄; 天谷 政樹
Annals of Nuclear Energy, 139, p.107268_1 - 107268_9, 2020/05
被引用回数：3 パーセンタイル：35.51(Nuclear Science & Technology)This paper reports a computer-code analysis on the base-irradiation behavior of the chromia-and-alumina-doped BWR rod irradiated to 64 GWd/t in Oskarshamn-3, Sweden, and subjected to the reactivity-initiated-accident (RIA) test OS-1, which resulted in a fuel failure due to pellet-cladding mechanical interaction (PCMI) at the lowest fuel-enthalpy increase in all the BWR tests ever performed. The inverse calculation which utilized post-irradiation examination data as its constraint conditions revealed that the OS-1 rod had very likely experienced more intense PCMI loading due to higher swelling rate during base irradiation than other BWR rods subjected to previous RIA tests and thus had been prone to experience enhanced radial-hydride formation. The significant difference in the cladding hoop-stress more than 50 MPa discriminates the OS-1 rod from other BWR rods and supports the interpretation that enhanced radial-hydrides formation differentiated the PCMI-failure behavior observed in the test OS-1 from the previous BWR-fuel tests.
Naeem, M.*; He, H.*; Zhang, F.*; Huang, H.*; Harjo, S.; 川崎 卓郎; Wang, B.*; Lan, S.*; Wu, Z.*; Wang, F.*; et al.
Science Advances (Internet), 6(13), p.eaax4002_1 - eaax4002_8, 2020/03
被引用回数：147 パーセンタイル：99.09(Multidisciplinary Sciences)High-entropy alloys exhibit exceptional mechanical properties at cryogenic temperatures, due to the activation of twinning in addition to dislocation slip. The coexistence of multiple deformation pathways raises an important question regarding how individual deformation mechanisms compete or synergize during plastic deformation. Using in situ neutron diffraction, we demonstrate the interaction of a rich variety of deformation mechanisms in high-entropy alloys at 15 K, which began with dislocation slip, followed by stacking faults and twinning, before transitioning to inhomogeneous deformation by serrations. Quantitative analysis showed that the cooperation of these different deformation mechanisms led to extreme work hardening. The low stacking fault energy plus the stable face-centered cubic structure at ultralow temperatures, enabled by the high-entropy alloying, played a pivotal role bridging dislocation slip and serration.
岡崎 泰幸*; 林 久資*; 青柳 和平; 森本 真吾*; 進士 正人*
Proceedings of 5th ISRM Young Scholars' Symposium on Rock Mechanics and International Symposium on Rock Engineering for Innovative Future (YSRM 2019 and REIF 2019) (USB Flash Drive), 6 Pages, 2019/12
トンネルの支保工の設計の際、数値解析により掘削時の岩盤の挙動や支保工へ作用する応力が予想される。しかしながら、解析では、岩盤の持つ力学的な不均質性を考慮しない場合が通常である。そのため、解析では掘削時の岩盤挙動を正確に再現できていない可能性がある。そこで、本研究では、幌延深地層研究センターの深度350mの調査坑道を対象として、岩盤の持つ不均質性を考慮したトンネル掘削解析を実施した。結果として、調査坑道で計測されたような局所的に作用する支保工応力を再現するためには、岩盤の不均質性を考慮する必要があることが明らかとなった。また、不均質性の寸法の考慮も重要な要素であることが明らかとなった。
上地 俊*; 上地 宏*; 西村 昭彦
World Journal of Engineering and Technology, 7(4), p.559 - 571, 2019/11
水飲み鳥の動作について熱力学的モデルを論じる。熱力学的モデルから導かれる数学的表現を数値計算の上で明示した。これは機械的な動作と熱力学的な動作の違いに関して基礎的な理解を得ることに助けとなる。機械的な繰り返し動作と熱力学的な繰り返し動作の間には数学的にも物理的にも違いが存在する。この水飲み鳥の工程は本論文で示した手法で環境エネルギー発電に対して適用可能である。
北垣 徹; 池内 宏知; 矢野 公彦; Brissonneau, L.*; Tormos, B.*; Domenger, R.*; Roger, J.*; 鷲谷 忠博
Journal of Nuclear Science and Technology, 56(9-10), p.902 - 914, 2019/09
被引用回数：7 パーセンタイル：61.94(Nuclear Science & Technology)Characterization of fuel debris is required to develop fuel debris removal tools. Especially, knowledge pertaining to the characteristics of molten core-concrete interaction (MCCI) product is needed because of the limited information available at present. The samples of a large-scale MCCI test performed under quenching conditions, VULCANO VW-U1, by CEA were analyzed to evaluate the characteristics of the surface of MCCI product generated just below the cooling water. As a result, the microstructure of the samples were found to be similar despite the different locations of the test sections. The Vickers hardness of each of the phases in these samples was higher than that of previously analyzed samples in another VULCANO test campaign, VBS-U4. From the comparison between analytical results of VULCANO MCCI test product, MCCI product generated under quenching condition is homogeneous and its hardness could be higher than that of the bulk MCCI product.
青柳 和平; 常盤 哲也*; 佐藤 稔紀; 早野 明
Proceedings of 2019 Rock Dynamics Summit in Okinawa (USB Flash Drive), p.682 - 687, 2019/05
本研究では、幌延深地層研究センターの発破掘削で施工された東立坑および機械掘削で施工された換気立坑において、掘削損傷領域の定量的な違いを検討することを目的とした。両立坑で実施した壁面観察の結果、発破掘削では、機械掘削と比較して、掘削に伴い発生したと考えられる割れ目が多く確認された。また、壁面で計測された弾性波速度に関しても、発破掘削で施工された東立坑の方が、機械掘削で施工された換気立坑よりも小さい値であった。これらの結果から、発破掘削の方が壁面岩盤に与える損傷の度合いが大きいことがわかった。さらに、発破掘削では、切羽前方の岩盤を補強するような支保パターンが、壁面の損傷を低減するのに最適である可能性が示された。
飛田 徹; 西山 裕孝; 鬼沢 邦雄
JAEA-Data/Code 2018-013, 60 Pages, 2018/11
JAEA-Data-Code-2018-013.pdf:1.67MB
原子炉圧力容器の健全性を判断する上で、破壊靱性をはじめとする材料の機械的特性は重要な情報となる。本レポートは、日本原子力研究開発機構が取得した中性子照射材を含む原子炉圧力容器鋼材の機械的特性、具体的には引張試験, シャルピー衝撃試験, 落重試験及び破壊靱性試験の公開データをまとめたものである。対象とした材料は、初期プラントから最新プラント相当の不純物含有量及び靱性レベルで製造されたJIS SQV2A(ASTM A533B Class1)相当の5種類の原子炉圧力容器鋼である。また母材に加え、原子炉圧力容器の内張りとして用いられている2種類のステンレスオーバーレイクラッド材の機械的特性データについても記載した。これらの機械的特性データは、材料ごとにグラフで整理するとともに今後のデータの活用しやすさを考慮して表形式でリスト化した。
北垣 徹; 池内 宏知; 矢野 公彦; 荻野 英樹; Haquet, J.-F.*; Brissonneau, L.*; Tormos, B.*; Piluso, P.*; 鷲谷 忠博
Progress in Nuclear Science and Technology (Internet), 5, p.217 - 220, 2018/11
Characterization of the fuel debris is required to develop fuel debris removal tools for the decommissioning of Fukushima Daiichi Nuclear Power Plant (1F). In this study, the VULCANO MCCI test, VBS-U4, was selected as 1F similar conditions and the characteristics of the samples were examined. In the molten pool sample, the round-edged corium-rich oxides region, with diameters of 1-10 mm, is surrounded by a concrete-rich oxide region. It shows convection of the molten pool. Other samples also show the features of the MCCI progression. The main chemical forms of the samples are SiO, (U,Zr)O, Fe and so on. The microstructure of the samples is heterogeneous structure composed of these phases. The difference in Vickers hardness between the metallic phases and the oxide phases is a distinctive characteristic. It can be noted that the heterogeneous distribution of metallic phases in 1F MCCI products interrupt with the removal operation such as by damaging the core-boring bit.
Dost
l, M.*; Rossiter, G.*; Dethioux, A.*; Zhang, J.*; 天谷 政樹; Rozzia, D.*; Williamson, R.*; Kozlowski, T.*; Hill, I.*; Martin, J.-F.*
Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10
The benchmark on PCMI was initiated by OECD/NEA Expert Group on Reactor Fuel Performance (EGRFP) in June 2015 and is currently in the latter stages of compiling results and preparing the final report. The aim of the benchmark is to improve understanding and modelling of PCMI amongst NEA member organisations. This is being achieved by comparing PCMI predictions of different fuel performance codes for a number of cases. Two of these cases are hypothetical cases aiming to facilitate understanding of the effects of code-to-code differences in fuel performance models. The two remaining cases are actual irradiations, where code predictions are compared with measured data. During analysis of participants' results of the hypothetical cases, the assumptions for number of radial pellet cracks and the pellet-clad friction coefficient (which can be zero, finite or infinite) were identified to be important factors in explaining differences between predictions once pellet-cladding contact occurs. However, these parameters varied in the models and codes used originally by the participants. This fact led to the extension of the benchmark by inclusion of two additional cases, where the number of radial pellet cracks and three different values of the friction coefficient were prescribed in the case definition. Seven calculations from six organisations contributed results were compared and analysed in this paper.
北垣 徹; 星野 貴紀; 矢野 公彦; 岡村 信生; 小原 宏*; 深澤 哲生*; 小泉 健治
Journal of Nuclear Engineering and Radiation Science, 4(3), p.031011_1 - 031011_7, 2018/07
Evaluation of fuel debris properties is required to develop fuel debris removal tools for the decommissioning of Fukushima Daiichi Nuclear Power Plant (1F). In this research, the mechanical properties of cubic (U,Zr)O samples containing 10-65% ZrO are evaluated. In case of the (U,Zr)O samples containing less than 50% ZrO, Vickers hardness and fracture toughness increased, and the elastic modulus decreased slightly with increasing ZrO content. Moreover, all of those values of the (U,Zr)O samples containing 65% ZrO increased slightly compared to (U,Zr)O samples containing 55% ZrO. However, higher Zr content (exceeding 50%) has little effect on the mechanical properties. This result indicates that the wear of core-boring bits in the 1F drilling operation will accelerate slightly compared to that in the TMI-2 drilling operation.
上羽 智之; 根本 潤一*; 石谷 行生*; 伊藤 昌弘*
Nuclear Engineering and Design, 331, p.186 - 193, 2018/05
被引用回数：4 パーセンタイル：38.58(Nuclear Science & Technology)高速炉MOX燃料ピンの照射挙動を計算するコードと燃料ピン内のCsの挙動に特化して計算するコードを連成することにより、Cs挙動が燃料ピンの熱・機械的挙動に及ぼす影響を解析できるようにした。連成した計算コードを高燃焼度MOX燃料ピンの照射挙動解析に適用し、Csの燃料ピン内軸方向分布やCs化合物による燃料ペレットと被覆管の機械的相互作用などを評価した。
廣岡 瞬; 加藤 正人
Journal of Nuclear Science and Technology, 55(3), p.356 - 362, 2018/03
被引用回数：8 パーセンタイル：62.99(Nuclear Science & Technology)密度, O/MおよびPu含有率をパラメータとして、MOXの音速測定を行った。これらのパラメータの影響はそれぞれ一次関数でよくフィッティングすることができ、MOXの音速を評価するフィッティング式が得られた。得られた音速のデータから機械物性が評価され、例として、密度低下によりヤング率は急激に低下する結果が得られた。また、過去に報告されている熱膨張のデータを用いることにより、ヤング率の温度依存性を評価した。温度上昇によりヤング率が低下し、文献値とよく一致する結果が得られた。
