在FREYA项目框架内使用面积法对次临界VENUS-F堆芯进行反应性监测
Reactivity monitoring using the area method for the subcritic al VENUS-F core within the framework of the FREYA Project
摘要：
加速器驱动系统（ADS）可用于焚烧次要锕系元素，因此部分有助于解决核废物管理问题。ADS由一个次临界快堆和一个粒子加速器通过一个重物质溅射靶耦合组成。在线反应性监测是一个严重的问题，这样的ADS的安全。为了研究这种监测的方法，在FP 6-IP-EUROTRANS方案的框架内，在几内亚设施进行了零功率实验。这些实验已经在FREYA FP 7项目中完成。GUINEVERE设施位于Mol（比利时）的SCK-CEN工厂。它将VENUS-F次临界快核与GENEPI-3C加速器耦合。后者提供一束氘，通过氚化靶上的聚变反应转化为14 MeV的中子。本文介绍了ADS在线反应性监测的研究方法之一，必须在FREYA项目的程序中进行验证。它描述了当脉冲中子源实验使用所谓的面积法进行分析时所获得的结果，以估计VENUS-F反应堆的几个次临界配置的反应性，keff= 0.96左右。首先介绍了几内亚的设施。然后，一般的考虑后，面积法，它的应用于测量的中子粒子数时间减少谱脉冲后，由几个裂变室分布在整个反应堆的结果进行了讨论。最后提取的反应性值进行比较，使用修改的源乘法（MSM）方法获得的静态反应性值。
英文摘要：
Accelerator-Driven Systems (ADS) could be employed to incinerate minor actinides and so partly contribute to answer the problem of nuclear waste management. An ADS consists of the coupling of a subcritical fast reactor to a particle accelerator via a heavy material spallation target. The on-line reactivity monitoring of such an ADS is a serious issue regarding its safety. In order to study the methodology of this monitoring, zero-power experimentswere undertaken at the GUINEVERE facility within the framework of the FP6-IP-EUROTRANS programme. Such experiments have been under completion within the FREYA FP7 project. The GUINEVERE facility is hosted at the SCK-CEN site in Mol (Belgium). It couples the VENUS-F subcritical fast core with the GENEPI-3C accelerator. The latter delivers a beam of deuterons, which are converted into 14-MeV neutrons via fusion reactions on a tritiated target. This paper presents one of the investigated methods for ADS on-line reactivity monitoring which has to be validated in the program of the FREYA project. It describes the results obtained when Pulsed Neutron Source experiments are analysed using the so called Area Method, in order to estimate the reactivity of a few sub-critical configurations of the VENUS-F reactor, around keff= 0.96. First the GUINEVERE facility is described. Then, following general considerations on the Area method, the results of its application to the neutron population time decrease spectra measured after a pulse by several fission chambers spread out over the whole reactor are discussed. Finally the reactivity values extracted are compared to the static reactivity values obtained using the Modified Source Multiplication (MSM) method.
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