OECD/NEA benchmark on pellet-clad mechanical interaction modelling with fuel performance codes; Influence of pellet geometry and gap size

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.

The Effect of base irradiation on failure behaviors of UO 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

AA2019-0372.pdf:0.81MB

https://doi.org/10.1016/j.anucene.2019.107268

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.

Proceedings of the 11th International Workshop on Ceramic Breeder Blanket Interactions; December 15 - 17, 2003, Tokyo, Japan

榎枝 幹男

JAERI-Conf 2004-012, 237 Pages, 2004/07

JAERI-Conf-2004-012.pdf:44.1MB

本報文集は、「IEA核融合炉工学に関する実施取り決め」に基づくセラミック増殖材ワークショップ及び日米核融合共同研究の一環として開催された「第11回セラミック増殖材ブランケット相互作用国際ワークショップ」の報文をまとめたものである。本ワークショップでは、欧州連合,ロシア,日本のセラミック増殖ブランケットの設計,HICU, EXOTIC-8, IVV-2Mによる照射試験の最新の成果,LiTiO等のトリチウム放出挙動のモデリング,LiTiOとLiSiO微小球の製造技術開発と物性値研究,LiTiOとLiSiO微小球充填層の熱機械挙動測定とモデリングに関する研究,境界テーマとして、ブランケット筐体製作技術開発,核融合中性子によるブランケットモックアップの中性子工学実験,トリチウム回収システム開発、などについての研究開発の現状と今後の課題についての情報交換が行われた。

SMESモデルコイル; 機械的特性

和智 良裕*; 花井 哲*; 河合 正道*; 小野 通隆*; 平岸 政洋*; 浜島 高太郎*; 石尾 光太郎*; 中嶋 秀夫; 辻 博史; 篠田 公之*; et al.

低温工学, 33(7), p.479 - 484, 1998/00

https://doi.org/10.2221/jcsj.33.479

SMESモデルコイルの機械的特性を、通電中の歪、変位を測定することにより評価した。変位は弾性的であり、歪は解析結果と一致して十分低かった。よって機械的強度に問題がないことが実証できた。また、アコースティック・エミッション(AE)センサーでは、初期励磁とそれ以降では、AE信号が激減すること、コイル巻線部とサポート部で、AE信号の周波数が異なることが判明した。

DPC-TJ実験結果; 機械的特性

和智 良裕*; 向 博志*; 小野 通隆*; 真田 芳直*; 藤岡 勉*; 中嶋 秀夫; 杉本 誠; 小泉 興一; 吉田 清; 大内 英義*; et al.

低温工学, 27(3), p.245 - 251, 1992/00

https://doi.org/10.2221/jcsj.27.245

原研と東芝が共同研究にて製作したDPC-TJコイルの実験結果のうち、機械的特性について述べる。DPC-TJコイルは、核融合炉用超電導コイルの高平均電流密度化を目指したコイルであり、プリフォームド・アーマ方式を考案し採用することによって、高平均電流密度と高剛性を両立させた設計となっている。今回の通電実験の結果、剛性が高いことが示されたとともに、機械的に安定したコイルであることが示された。

Comparative analysis on base-irradiation behaviors of OS-1 test rod and other BWR-fuel rods subjected to previous NSRR tests

宇田川 豊

no journal, , 

This presentation 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 PCMI-related parameters between the OS-1 rod and other BWR rods 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.