Modelling of HTR (High Temperature Reactor) Pebble-Bed 10 MW to Determine Criticality as A Variations of Enrichment and Radius of the Fuel (Kernel) With the Monte Carlo Code MCNP4C

Hammam Oktajianto, E. Setiawati, V. Richardina
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引用次数: 7

Abstract

Gas-cooled nuclear reactor is a Generation IV reactor which has been receiving significant attention due to many desired characteristics such as inherent safety, modularity, relatively low cost, short construction period, and easy financing. High temperature reactor (HTR) pebble-bed as one of type of gas-cooled reactor concept is getting attention. In HTR pebble-bed design, radius and enrichment of the fuel kernel are the key parameter that can be chosen freely to determine the desired value of criticality. This paper models HTR pebble-bed 10 MW and determines an effective of enrichment and radius of the fuel (Kernel) to get criticality value of reactor. The TRISO particle coated fuel particle which was modelled explicitly and distributed in the fuelled region of the fuel pebbles using a Simple-Cubic (SC) lattice. The pebble-bed balls and moderator balls distributed in the core zone using a Body-Centred Cubic lattice with assumption of a fresh fuel by the fuel enrichment was 7-17% at 1% range and the size of the fuel radius was 175-300 µ m at 25 µ m ranges. The geometrical model of the full reactor is obtained by using lattice and universe facilities provided by MCNP4C. The details of model are discussed with necessary simplifications. Criticality calculations were conducted by Monte Carlo transport code MCNP4C and continuous energy nuclear data library ENDF/B-VI. From calculation results can be concluded that an effective of enrichment and radius of fuel (Kernel) to achieve a critical condition was the enrichment of 15-17% at a radius of 200 µ m, the enrichment of 13-17% at a radius of 225 µ m, the enrichments of 12-15% at radius of 250 µ m, the enrichments of 11-14% at a radius of 275 µ m and the enrichment of 10-13% at a radius of 300 µ m, so that the effective of enrichments and radii of fuel (Kernel) can be considered in the HTR 10 MW. Keywords —MCNP4C, HTR, enrichment, radius, criticality
HTR(高温堆)球床10mw模型在燃料(核)浓缩和半径变化下确定临界的蒙特卡罗代码MCNP4C
气冷核反应堆是第四代反应堆,由于其固有的安全性、模块化、相对较低的成本、较短的建设周期和容易融资等特点而备受关注。球床高温堆作为气冷堆的一种,其概念日益受到人们的关注。在高温气冷堆球床设计中,核燃料堆芯半径和富集度是确定理想临界值的关键参数,可以自由选择。本文对10 MW高温气冷堆球床进行建模,确定了浓缩系数和燃料(核)半径,得到了反应堆的临界值。三iso颗粒包覆燃料颗粒,采用简单立方晶格分布在燃料卵石的燃料区。球床球和慢化球采用体心立方晶格分布在核心区,假设燃料富集为新鲜燃料,在1%范围内为7-17%,在25µm范围内燃料半径为175-300µm。利用MCNP4C提供的晶格和宇宙装置,得到了全堆的几何模型。讨论了模型的细节,并作了必要的简化。临界计算采用蒙特卡罗传输代码MCNP4C和连续能核数据库ENDF/B-VI进行。从计算结果可以得出结论,一个有效的浓缩和燃料(内核)半径达到临界条件是15 - 17%的浓缩在一个半径为200µm, 13 - 17%的浓缩在一个半径为225µm, 12 - 15%的充实半径250µm, 11 - 14%的充实的半径275µm和10 - 13%的浓缩在一个半径为300µm,这样有效的充实和半径的燃料(内核)可以被认为是在HTR 10兆瓦。关键词-MCNP4C, HTR,富集,半径,临界
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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