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Out of pile tritium release behaviour and microscopic investigation of lithium metatitanate irradiated in the High Flux Reactor in Petten

机译:佩滕高通量反应堆辐照的pile外释放行为和微观研究

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摘要

The irradiation experiment EXOTIC 9/1 is the latest in a series of EXOTICs that has been irradiated in the high flux reactor in Petten and studies tritium release and inventory in ceramic pebbles containing lithium, which are key properties for the fusion fuel cycle. New production routes of pebbles are developed, leading to different thermomechanical and tritium release properties. The pebbles, produced by an extrusion-spheroidisation-sintering process at CEA in 2004, differ in porosity and density from the Li_2TiO_3 ceramics tested in the previous EXOTIC 8 programme. The pebbles have a diameter in the range from 0.6 to 0.8 mm, a high density (93% TD) and an open porosity of 1.7%. The pebbles mainly differ in enrichment (7.5% and 30% ~6 Li-enrichment).During irradiation of 300 Full Power Days in the HFR in Petten, the temperature in EXOTIC 9/1 was varied between 340 and 580℃ The final irradiation (EOL) temperature is 480℃ and the average total ~6Li burn-up is 3%. The total measured activity from tritium during irradiation is 220.42Ci.After the completion of the irradiation, the out of pile release behaviour was studied by temperature programmed desorption (TPD). More specifically, the remaining tritium inventory in the pebbles and the activation energy of different release mechanisms were studied. The TPD was carried out for Li_2TiO_3 samples with 7.5% (natural) and 30% (enriched)~6Li-abundance and revealed very different curves, indicating that the materials have different release mechanisms. Dissolving the irradiated samples in hydrogen peroxide indicates that no tritium is left in the pebbles after TPD. Results from optical microscopy show it is likely that more intense bubble formation has taken place in the enriched samples, compared to the natural samples.
机译:辐照实验EXOTIC 9/1是已在Petten高通量反应堆中辐照的一系列EXOTIC中的最新一项,它研究了含锂陶瓷小卵石中的release释放和存量,这是聚变燃料循环的关键特性。开发了卵石的新生产路线,从而导致了不同的热机械和tri释放特性。 2004年在CEA上通过挤压球化烧结工艺生产的卵石,其孔隙率和密度与先前在EXOTIC 8程序中测试的Li_2TiO_3陶瓷不同。卵石的直径在0.6到0.8毫米之间,密度高(TD为93%),开孔率为1.7%。鹅卵石的富集主要不同(7.5%和30%〜6 Li富集)。在Petten的HFR中照射300个全功率日期间,EXOTIC 9/1的温度在340至580℃之间变化。 EOL)温度为480℃,平均约6Li燃尽率为3%。辐照过程中测得的activity活度总和为220.42Ci。辐照完成后,通过程序升温脱附(TPD)研究了绒头的释放行为。更具体地说,研究了卵石中剩余的inventory存量和不同释放机制的活化能。对具有7.5%(天然)和30%(富集)〜6Li丰度的Li_2TiO_3样品进行了TPD,揭示了截然不同的曲线,表明材料具有不同的释放机理。将辐照的样品溶于过氧化氢表明,TPD后,鹅卵石中没有残留tri。光学显微镜的结果表明,与天然样品相比,富集样品中可能形成了更强烈的气泡。

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  • 来源
    《Fusion Engineering and Design》 |2010年第9期|p.1143-1146|共4页
  • 作者单位

    NRG-Petten, P.O. Box 25,1755ZG Petten, The Netherlands;

    NRG-Petten, P.O. Box 25,1755ZG Petten, The Netherlands;

    NRG-Petten, P.O. Box 25,1755ZG Petten, The Netherlands;

    NRG-Petten, P.O. Box 25,1755ZG Petten, The Netherlands;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    fusion; HCPB; pebble bed; tritium release; inventory;

    机译:融合HCPB;卵石床release释放;库存;
  • 入库时间 2022-08-18 00:39:48

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