首页> 外文会议>International conference on the physics of reactors;PHYSOR 2012 >POWER TRANSIENT ANALYSES OF EXPERIMENTAL IN-REFLECTOR DEVICES DURING SAFETY SHUTDOWN IN JULES HOROWITZ REACTOR (JHR)
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POWER TRANSIENT ANALYSES OF EXPERIMENTAL IN-REFLECTOR DEVICES DURING SAFETY SHUTDOWN IN JULES HOROWITZ REACTOR (JHR)

机译:JULES HOROWITZ反应器(JHR)安全关闭期间实验性反射器设备的功率瞬态分析

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The Jules Horowitz Reactor (JHR) is designed to be a 100 MW material testing reactor (MTR) and it is expected to become the reference facility in the framework of European nuclear research activity. As the core neutron spectrum is quite fast, several experimental devices concerning fuel studies have been conceived to be placed in the reflector in order to exploit a proper thermal neutron flux irradiation. Since the core power is relatively high, the neutronic coupling between the reactor core and the reflector devices has to be taken into account for different rod insertions. In fact the thermal power produced within the fuel samples is considerable. Heat removal during shutdown is a main topic in nuclear safety and it is worth to analyse thermal power transients in fuel samples as well. Here a thermal hydraulic model for JHR core is proposed aiming at a simple and representative description as far as reactivity feedbacks are concerned. Then it is coupled with a neutronic pointwise kinetics analysis by means of the DULCINEE code to compute core power transient calculations. Moreover, some reflector-core coupling evaluations are performed through Monte Carlo method using the TRIPOLI 4.7 code. The JHR equilibrium cycle is considered with respect to four fuel compositions namely Beginning of Cycle (BOC), Xenon Saturation Point (XSP), Middle of Cycle (MOC) and End of Cycle (EOC). Then thermal power transients in the experimental reflector devices are evaluated during safety shutdowns and they are verified for all these cycle steps.
机译:Jules Horowitz反应堆(JHR)设计为100兆瓦材料测试反应堆(MTR),有望成为欧洲核研究活动框架内的参考设施。由于核心中子谱非常快,因此已考虑将一些与燃料研究有关的实验装置放置在反射器中,以便利用适当的热中子通量辐射。因为堆芯功率相对较高,所以对于不同的杆插入,必须考虑反应堆堆芯与反射器装置之间的中子耦合。实际上,燃料样品中产生的热功率是相当大的。停机期间的排热是核安全中的一个主要主题,也有必要分析燃料样品中的热能瞬变。在此,针对反应性反馈,针对简单而有代表性的描述,提出了用于JHR岩心的热工水力模型。然后通过DULCINEE代码与中子点动力学分析相结合,以计算核心功率瞬变计算。此外,使用TRIPOLI 4.7代码通过蒙特卡洛方法进行了一些反射镜-铁心耦合评估。考虑到四种燃料成分的JHR平衡循环,即循环开始(BOC),氙饱和点(XSP),循环中间(MOC)和循环结束(EOC)。然后在安全关闭期间评估实验性反射器设备中的热功率瞬变,并针对所有这些循环步骤进行验证。

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