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Comparison of two irradiation testing results of HTR-10 fuel spheres

机译:HTR-10燃料球的两次辐照测试结果比较

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In order to study the irradiation performance of fuel spheres for the 10 MW high-temperature gas-cooled reactor (HTR-10), two in-pile irradiation tests were performed. The first irradiation test was performed in the Russian reactor IW-2M from July 2000 to February 2003. The four irradiated fuel spheres were randomly taken from the first product batches. The central temperature of irradiated fuel spheres during this irradiation was kept between 950 and 1050℃. The maximum burnup of the irradiated spheres was 107,000 MWd/tU and the maximum fast neutron fluence (E>0.1 MeV)wasl.31 × 10~(25) m~(-2). The release-to-birth rate ratios (R/B)ofKr and Xe fission products were 10~(-7) 10~(-5). The second irradiation test was performed in HFR Petten (HFR-EU1) from September 29, 2006 to February 19, 2010. Experiment HFR-EU1 consisted of 3 German AVR pebbles and 2 INET pebbles. The two INET pebbles were randomly taken from the latest production batch. The surface temperature of pebble INET 2 during irradiation was approx. 940 ℃. The experiment was performed in two campaigns from 29 September 2006 to 24 February 2008 (12 reactor cycles of 28 days) and continued from 19 October 2009 to 19 February 2010(4 reactor cycles). Up to end of irradiation, the experiment had accumulated 16 reactor cycles totaling 445 efpd and calculated burnup and maximum fast neutron fluence (E> 0.1 MeV) were 9.3% (pebble INET 1) and 11.6%FIMA (pebble INET 2) and about 4.95 × 10~(25) m~(-2), respectively. At end of irradiation, based on~(85m)Kr, R/B of approx. 8 × 10~(-8) was measured. The second irradiation test results are much better than the first. The irradiated sample manufacture technology and characterization, irradiation conditions and results of two irradiation tests are compared in detail in this paper.
机译:为了研究10 MW高温气冷堆(HTR-10)的燃料球辐照性能,进行了两次堆内辐照试验。从2000年7月至2003年2月,在俄罗斯反应堆IW-2M中进行了首次辐照试验。从第一批产品中随机抽取了四个辐照燃料球。辐照过程中被辐照的燃料球的中心温度保持在950至1050℃之间。辐照球的最大燃耗为107,000 MWd / tU,最大快中子注量(E> 0.1 MeV)为31×10〜(25)m〜(-2)。 Kr和Xe裂变产物的释出率(R / B)为10〜(-7)10〜(-5)。第二次辐射测试于2006年9月29日至2010年2月19日在HFR Petten(HFR-EU1)中进行。实验HFR-EU1由3个德国AVR卵石和2个INET卵石组成。这两个INET卵石是从最新的生产批次中随机抽取的。卵石INET 2在辐照过程中的表面温度约为。 940℃。该实验在2006年9月29日至2008年2月24日(12个反应堆周期为28天)的两个活动中进行,并从2009年10月19日至2010年2月19日(4个反应堆周期)继续进行。到辐照结束,该实验已累积了16个反应堆循环,总计445 efpd,计算出的燃耗和最大快中子通量(E> 0.1 MeV)分别为9.3%(卵石INET 1)和11.6%FIMA(卵石INET 2),约为4.95。 ×10〜(25)m〜(-2)辐照结束时,基于〜(85m)Kr,R / B约为测量为8×10〜(-8)。第二次辐照测试结果比第一个要好得多。本文对辐照样品的制备技术,表征,辐照条件和两次辐照试验的结果进行了比较。

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  • 来源
    《Nuclear Engineering and Design 》 |2012年第10期| p.453-458| 共6页
  • 作者单位

    Institute of Nuclear Energy Technology, Tsinghua University, Beijing 102201, China;

    Institute of Nuclear Energy Technology, Tsinghua University, Beijing 102201, China;

    Institute of Nuclear Energy Technology, Tsinghua University, Beijing 102201, China;

    Institute of Nuclear Energy Technology, Tsinghua University, Beijing 102201, China;

    Institute of Nuclear Energy Technology, Tsinghua University, Beijing 102201, China;

  • 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
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