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Database for WWER-1000 Reactor Pressure Vessel IAEA Regional Project RER 4/017

机译:WWER-1000反应器压力表数据库IAEA区域项目RER 4/017

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A review of the results obtained in the framework of the Project is presented in the paper. The database consists of experimental data obtained in a model of WWER-1000 assembled in the LR-0 experimental reactor in NRI. The differential neutron spectra measurements were carried out over the water layer between the barrel simulator and reactor pressure vessel (RPV) simulator and over the RPV simulator thickness. The core power distribution was measured by means of gamma scanning of fuel elements (several hundreds of elements for the radial distribution and several tens for the axial one). The core power distribution calculations were done by MOBY DICK (2D several groups, diffusion code) and the Monte Carlo Code MCU -RFFI/A, the transport calculations were performed with deterministic codes in laboratories of the participating countries. The neutron spectra were compared in BUGLE 96 format.
机译:审查在该项目的框架中获得的结果。该数据库由在NRI的LR-0实验反应器中组装的WWER-1000模型中获得的实验数据组成。在桶模拟器和反应堆压力容器(RPV)模拟器(RPV)模拟器之间的水层和RPV模拟器厚度之间进行差分中子谱测量。通过燃料元件的伽马扫描(用于径向分布的数百个元件和轴向的几十)来测量芯功率分布。核心配电计算由Moby Dick(2D几个组,扩散码)和蒙特卡罗代码MCU -RFFI / A进行,以参与国的实验室中的确定性码进行运输计算。中子谱在Bugle 96格式进行比较。

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