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論文

Development of experimental technology for simulated fuel-assembly heating to address core-material-relocation behavior during severe accident

阿部 雄太; 山下 拓哉; 佐藤 一憲; 中桐 俊男; 石見 明洋

Journal of Nuclear Engineering and Radiation Science, 6(2), p.021113_1 - 021113_9, 2020/04

The authors are developing an experimental technology for simulating severe accident (SA) conditions using simulate fuel material (ZrO$$_{2}$$) that would contribute, not only to Fukushima Daiichi (1F) decommissioning, but also to enhance the safety of worldwide existing and future nuclear power plants through clarification of accident progression behavior. Nontransfer (NTR) type plasma, which has been in practical use with a large torch capacity as high as 2 MW, has the potential to heat subject materials to very high temperatures without selecting the target to be heated. When simulating 1F with SA code, the target of this core-material-melting and relocation (CMMR) experiment was to confirm that NTR plasma has a sufficient heating performance realizing large temperature gradients ($$>$$ 2000 K/m) expected under 1F conditions. The authors selected NTR-type plasma-heating technology that has the advantage of continuous heating in addition to its high-temperature level. The CMMR-2 experiments were carried out in 2017 applying the improved technology (higher heating power and controlled oxygen concentration). The CMMR-2 experiment adopted a 30-min heating period, wherein the power was increased to a level where a large temperature gradient was expected at the lower part of the core under actual 1F accident conditions. Most of the control blade and channel box migrated from the original position. After heating, the simulated fuel assembly was measured by X-ray computed tomography (CT) technology and by electron probe micro-analyzer (EPMA). CT pictures and elemental mapping demonstrated its excellent performance with rather good precision. Based on these results, an excellent perspective, in terms of applicability of the NTR-type plasma-heating technology to the SA experimental study, was obtained.

論文

Development of experimental technology for simulated fuel-assembly heating to address core-material-relocation behavior during severe accident

阿部 雄太; 山下 拓哉; 佐藤 一憲; 中桐 俊男; 石見 明洋; 永江 勇二

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 9 Pages, 2018/07

Authors are developing an experimental technology to realize experiments simulating Severe Accident (SA) conditions using simulant fuel material (ZrO$$_{2}$$ with slight addition of MgO for stabilization) that would contribute not only to Fukushima Daiichi (1F) decommissioning but also to enhance the safety of worldwide existing and future nuclear power plants through clarification of the accident progression behavior. Based on the results of the prototype test, improvement of plasma heating technology was conducted. The Core Material Melting and Relocation (CMMR)-1/-2 experiments were carried out in 2017 with the large-scale simulated fuel assembly (1 m $$times$$ 0.3 m $$phi$$) applying the improved technology (higher heating power and controlled oxygen concentration). In these two tests, heating history was different resulting basically in similar physical responses with more pronounced material melting and relocation in the CMMR-2 experiment. The CMMR-2 experiment is selected here from the viewpoint of establishing an experimental technology. The CMMR-2 experiment adopted 30-min heating period, the power was increased up to a level so that a large temperature gradient ($$>$$ 2,000 K/m) expected at the lower part of the core in the actual 1F accident conditions. Most of the control blade and the channel box migrated from the original position. After the heating, the simulated fuel assembly was measured by the X-ray Computed Tomography (CT) technology and by Electron Probe Micro Analyzer (EPMA). CT pictures and elemental mapping demonstrated its excellent performance with rather good precision. Based on these results, an excellent perspective in terms of applicability of the non-transfer type plasma heating technology to the SA experimental study was obtained.

論文

Development of non-transfer type plasma heating technology to address CMR behavior during severe accident with BWR design conditions

阿部 雄太; 佐藤 一憲; 中桐 俊男; 石見 明洋; 永江 勇二

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 7 Pages, 2017/04

Authors are developing an experimental technology to realize experiments simulating severe accident conditions that would contribute not only to Fukushima Daiichi (1F) decommissioning but also to enhance safety of worldwide existing and future nuclear power plants through clarification of the accident progression behavior. In the first part of this program, called Phase I hereafter, a series of small-scale experiments (10 cm $$times$$ 10 cm $$times$$ 25 cmh) were performed in March 2015 and it was demonstrated that non-transfer (NTR) type plasma heating is capable of successfully melting the high melting-point ceramics. In order to confirm applicability of this heating technology to larger scale test specimens to address the experimental needs, authors performed a second series plasma heating tests in 2016, called Phase II hereafter, using a simulated fuel assembly with a larger size (100 cm $$times$$ 30 cm phi). In the phase II part of the program, the power was increased up to a level so that a large temperature gradient (2,000 K/m - 4,000 K/m) expected at the lower part of the core in the actual 1F accident conditions. After the heating, these test pieces were measured by the X-ray Computed Tomography (CT) technology. CT pictures demonstrated its excellent performance with rather good precision. Based on these results, basic applicability of the NTR plasma heating for the SA experimental study was confirmed. With the Phase II-type 100 cm-high test geometry, core material relocation (CMR) behavior within the active core region and its access to the core support structure region would be addressed. JAEA is also preparing for the next step large-scale tests using up to four simulated fuel assemblies covering the lower part of the active fuel and fully simulating the upper part of the lower core support structures addressing CMR behavior including core material relocation into the lower plenum.

報告書

土壌中の考古学的金属製品の腐食に関する調査(研究委託内容報告書)

本田 卓*; 山口 新吾*

JNC-TJ8400 2000-007, 200 Pages, 2000/02

JNC-TJ8400-2000-007.pdf:14.84MB

数百年以上にわたって土壌中に埋もれていた鉄製の考古遺物は、腐食による厚い錆層に覆われており金属鉄の残存状態や原形の推定が極めて難しい。本研究では約500$$sim$$1,000年前の遺跡から発掘された釜、短刀、釘などを対象に研究を実施した。(1)X線CT計測により錆層と鉄とを高精度に分離計測でき、更に鉄が残存しない場合も原形状を推定できること等を明らかにした。また、X線透過試験との比較も行った。(2)密度測定、付着物の化学分析を実施し、X線CT計測により得られた錆厚さから腐食量及び腐食速度の推定を行った。(3)同年代の鉄滓を評価し、古代鉄と現在の炭素鋼の性状の違いについて検討した。

口頭

改良ステンレス鋼燃料被覆管のBWR装荷に向けた研究開発,3-5; 溶接法・検査方法の検討

木村 晃彦*; 薮内 聖皓*; 坂本 寛*; 山下 真一郎; 草ヶ谷 和幸*

no journal, , 

軽水炉事故耐性型燃料被覆管の開発においては、接合技術が枢要な技術開発項目とされている。本研究では、ODS鋼被覆管の端栓溶接法として従来の被覆管に採用されているEB溶接法を用いて端栓溶接被覆管の端栓接合強度を評価し、さらに端栓部に対しX線CT検査を実施して接合強度と接合組織の相関を調べ、被覆管端栓接合条件について検討した。

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