原子能科学技术Issue(z2)：562-567,6.DOI:10.7538/yzk.2013.47.S1.0562
蒙特卡罗方法对钚燃料堆芯 VSOP 模型的验证
Verification of VSOP Model for Plutonium Fuel Core Based on Monte Carlo Method
摘要
Abstract
VSOP program package is widely used in the engineering design of the pebble bed high-temperature gas-cooled reactor with uranium fuel , but the applicability of VSOP code for pure plutonium fuel core is not completely proven . Uranium and plutonium were recycled from the 250 MW High-Temperature Gas-Cooled Reactor-Pebble-bed-Module (HTR-PM ) spent fuel from the U-Pu fuelled core ,and PuO2 and MOX fuel elements were designed based on this recycled plutonium and uranium .These fuel elements were used to build up a new PuO2 or MOX fuelled core with the same geometry of the original reactor .The random arrangement of coated fuel particles in the fuel pebbles and the random distribution of the fuel pebbles in the core were modeled as the repeated structure of regular shape in the Monte Carlo package MCNP .Based on the same reference of HTR reactor core ,the core effective multiplication factors from VSOP model and Monte Carlo model were compared ,and the causes of the differences were analyzed .Preliminary results show that the VSOP simulation result of the uranium fuel core accords well with the MCNP result ,and the VSOP result of the pure plutonium fuel core is about 2% lower than that of MCNP code .Preliminary results demonstrate the applicability of VSOP code for pure plutonium fuel core , and the improve suggestions of the VSOP code were given .关键词
高温气冷堆/球床/燃料循环/VSOP模型/蒙特卡罗方法Key words
high-temperature gas-cooled reactor/pebble bed/fuel cycle/VSOP model/Monte Carlo method分类
能源科技引用本文复制引用
位金锋,李富,孙玉良,张竞宇..蒙特卡罗方法对钚燃料堆芯 VSOP 模型的验证[J].原子能科学技术,2013,(z2):562-567,6.基金项目
国家重大科技专项经费资助项目 （）
