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Desain Teras dan Bahan Bakar Pltn Jenis Htr-pbmr pada Daya 50 Mwe dengan Menggunakan Program Srac2006

机译:使用Srac2006程序设计50 Mwe功率的梯田型和燃料型Htr-PBMR

摘要

DESIGN OF 50 MWe HTR-PBMR REACTOR CORE AND NUCLEAR POWER PLANT FUEL USING SRAC2006 PROGRAMME. This research aims to assess the design of core and fuel of nuclear power plant type High Temperature Reactor-Pebble Bed Modular Reactor 50 MWe from the Beginning of Life (BOL) to Ending of life (EOL) with eight years operating life. The parameters that need to be analyzed in this research are the temperature distribution inside the core, quantity enrichment of U235 , fuel composition, criticality, and temperature reactivity coefficient of the core. The research was conducted with a data set of core design parameters such as nuclides density, core and fuel dimensions, and the axial temperature distribution inside the core. Using SRAC2006 program package, the effective multiplication factor (keff) values obtained from the input data that has been prepared. The results show the value of the criticality of core is proportional to the addition of U235 enrichment. The optimum enrichment obtained at 10.125% without the use of burnable poison with an excess reactivity of 3.12% at BOL. The addition Gd2O3 obtained an optimum value of 12 ppm burnable poison with an excess reactivity 0.38 %. The use of Er2O3 with an optimum value 290 ppm has an excess reactivity 1.24% at BOL. The core temperature reactivity coefficient with and without the use of burnable poison has a negative values that indicates the nature of its inherent safety.
机译:使用SRAC2006程序设计50 MWe HTR-PBMR反应堆核和核电站燃料。这项研究旨在评估从生命周期(BOL)到寿命终止(EOL)具有八年运行寿命的50 MWe核电站型高温反应堆-卵石床模块化反应堆的核和燃料设计。该研究需要分析的参数是堆芯内部的温度分布,U235的数量富集,燃料成分,临界度和堆芯的温度反应系数。这项研究是使用一组核心设计参数(例如核素密度,核心和燃料尺寸以及核心内部的轴向温度分布)进行的。使用SRAC2006程序包,可以从已准备好的输入数据中获得有效乘数(keff)值。结果表明,堆芯临界值与添加U235富集成正比。在不使用可燃毒物且在BOL处有3.12%的过量反应性的情况下,最佳富集度为10.125%。添加的Gd2O3的最佳值为12 ppm的可燃毒物,反应活性为0.38%。最佳值为290 ppm的Er2O3在BOL时的过量反应性为1.24%。在使用和不使用可燃性毒药的情况下,核心温度反应系数具有负值,表明其固有安全性。

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