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HTR PEBBLE FUEL BURNUP EXPERIMENTAL BENCHMARK

机译:HTR燃料燃烧试验基准

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The HTR pebble fuel experiment HFR EUlbis was irradiated in the High Flux Reactor, Petten, The Netherlands, in 2004 and 2005. It consisted of five fuel pebbles from the German HTR program (GLE4 type, UO_2 fuel, 16.75% enrichment) and six minisamples (UO_2 fuel, 9.75% enrichment). Its instrumentation included three flux monitor sets. The experiment was loaded in a REFA-170 rig, surrounded by a strongly moderating filler element. The central fuel temperature was held at 1250°C during the irradiation. In the framework of the European RAPHAEL project, Post Irradiation Examination (PIE) has been done at NRG in Petten, The Netherlands and at JRC ITU in Karlsruhe, Germany. In Petten, flux monitor analysis has been done, whereas in Karlsruhe, a quantitative evaluation of γ-emitters was used to make a burn-up determination.A benchmark description based on this experiment has been written by NRG. Until now, five RAPHAEL project participants have modeled the experiment, each with their own neutronics code system. Participating codes are three versions of MONTEBURNS (MCNP with ORIGEN), MURE/MCNP and OCTOPUS (MCNP with FISPACT).The pebble burnup and isotopic inventories (Bq/gram initial HM) of selected fission products and actinides in the fuel pebble samples are both calculated and determined by gamma spectrometry, mass spectrometry and ion chromatography by JRC-ITU. Additionally, two participants calculated the flux monitor activities that were measured by NRG.A burnup measurement of 11.0 %FIMA by gamma spectrometry could be confirmed by calculation. Differences between the various modeling approaches and the experimental burn-up determination will be discussed.
机译:HTR卵石燃料实验HFR EUlbis于2004年和2005年在荷兰Petten的高通量反应堆中进行了辐照。该实验由德国HTR计划的五种燃料卵石(GLE4型,UO_2燃料,16.75%的浓缩度)和六个小样本组成。 (UO_2燃料,浓缩9.75%)。它的仪器包括三套磁通监测仪。将实验加载到REFA-170钻机中,并用强缓和的填充剂包围。在辐照期间,中央燃料温度保持在1250℃。在欧洲RAPHAEL项目的框架内,已经在荷兰佩滕的NRG和德国卡尔斯鲁厄的JRC ITU进行了辐照后检查(PIE)。在Petten中,已经进行了通量监测器分析,而在Karlsruhe中,使用了对γ发射体的定量评估来确定燃耗。 NRG已编写了基于该实验的基准描述。到目前为止,五个RAPHAEL项目参与者已经对实验进行了建模,每个参与者都有自己的中子学代码系统。参与代码是MONTEBURNS(带有ORIGEN的MCNP),MURE / MCNP和OCTOPUS(带有FISPACT的MCNP)的三个版本。 燃料卵石样品中选定裂变产物和act系元素的卵石燃尽和同位素清单(Bq /克初始HM)均通过伽马光谱法,质谱法和离子色谱法(通过JRC-ITU)进行计算和确定。此外,两名参与者还计算了由NRG测量的流量监控器活动。 可以通过计算确认通过伽马光谱法测得的燃耗为11.0%FIMA。将讨论各种建模方法与实验燃耗确定之间的差异。

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