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首页> 外文期刊>Annals of nuclear energy >Measurement of isothermal temperature reactivity coefficient at research reactor with IRT-4M fuel
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Measurement of isothermal temperature reactivity coefficient at research reactor with IRT-4M fuel

机译：用IRT-4M燃料测量研究堆的等温温度反应系数

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Transients analyses is of high importance for reactor safety studies. The temperature reactivity coefficients belong to key input parameters for such studies. However, the amount of experimental data for validation of such parameters for the conditions of research reactors operated with LEU fuel is limited. To improve the situation, a tailor-made experimental instrumentation has been recently developed at zero power research reactor VR-1 that allows for detailed measurement of temperature reactivity effects in lattices with IRT-4M fuel. The instrumentation enables by external water heater to change the temperature of fuel and surrounding water moderator in 2 × 2 positions of reactor grid in the range from 20 to 40 ℃. Using the instrumentation the isothermal temperature reactivity effect was measured for a group of four eight-tube fuel assemblies in the above mentioned temperature range. Results were compared to MCNP calculations with the precise model of the VR-1 reactor. The MCNP code was further used for dee-per analysis of experimental data.
机译：瞬态分析对于反应堆安全性研究非常重要。温度反应系数属于此类研究的关键输入参数。但是，用于验证使用低浓铀燃料运行的研究堆条件的此类参数的实验数据数量有限。为了改善这种情况，最近在零功率研究反应堆VR-1上开发了量身定制的实验仪器，该仪器可以详细测量IRT-4M燃料对晶格中温度反应性的影响。该仪器使外部热水器能够在20到40℃的范围内改变反应堆栅格的2×2位置的燃料和周围的水慢化剂的温度。使用仪器，在上述温度范围内，对一组四个八管燃料组件的等温温度反应效果进行了测量。将结果与使用VR-1反应堆的精确模型的MCNP计算结果进行比较。 MCNP代码进一步用于对实验数据进行更深入的分析。

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