The relationship between burnup and neutron emission intensity of the irradiated low-enrichment uranium oxide fuel was analyzed and studied.
对辐照过的低富集氧化铀燃料的燃耗与中子发射强度间的关系进行分析和研究。
In this paper, a set of important formulae for burnup determination of fuel element from HFETR are deduced and researched, and main formulae of ASTM E244 are reformed.
本文推导和研究了适用于高通量工程试验堆燃料元件燃耗测定的重要公式，并将ASTME244的公式作了重要修改。
For reactors loaded with fuel assemblies of different burnup, the evaluation model can te used to calculate core physical parameters such as core neutron multiplication factor, burnup increment, etc.
对于堆芯内布置不同燃耗深度的燃料元件的反应堆，应用本模型可以估算堆芯燃耗物理参数如：堆芯中子增殖系数、燃料元件燃耗增值等。
Because of increasing burnup of power reactor, more advanced technologies should be applied in the reprocessing of spent nuclear fuel.
由于核电站动力堆乏燃料的燃耗深，对乏燃料后处理工艺技术提出了更高要求。
It provided the basis for constructing the spent fuel critical experimental facility and development studies of burnup credit technology.
本文为以后建造乏燃料临界实验装置，开展燃耗信任制技术的综合研究打下了基础。
It provided the basis for constructing the spent fuel critical experimental facility and development studies of burnup credit technology.
本文为以后建造乏燃料临界实验装置，开展燃耗信任制技术的综合研究打下了基础。
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