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

作　　者：位金锋[1] 李富[2] 孙玉良[2] 张竞宇[2] 

机构地区：[1]中科华核电技术研究院有限公司,广东深圳518026 [2]清华大学核能与新能源技术研究院,北京100084

出　　处：《原子能科学技术》2013年第B12期562-567,共6页Atomic Energy Science and Technology

基　　金：国家重大科技专项经费资助项目(ZX06901)

摘　　要：VSOP程序广泛应用于高温气冷堆铀燃料堆芯设计,而对钚燃料堆芯未经充分验证。本文基于250MW球床模块式高温气冷堆示范电站HTR-PM铀钚循环乏燃料中的铀和钚,设计了PuO2和MOX燃料元件,将新设计的燃料元件重新装入与HTR-PM同样结构和尺寸的堆芯,分别形成纯钚燃料堆芯和MOX燃料堆芯。利用蒙特卡罗方法中规则的重复结构模拟包覆燃料颗粒在燃料球内的随机分布及燃料球在堆芯内的随机分布。针对同一参考堆芯,比较了VSOP模型和MCNP模型的有效增殖因数,并分析了产生差异的原因。结果显示,对于铀燃料堆芯,VSOP与MCNP程序计算结果符合较好;对于钚燃料堆芯,VSOP结果比MCNP结果小2%左右。初步验证了VSOP模型对钚燃料堆芯的可用性,提出了进一步改进VSOP程序的建议。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- Pebblekbed-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 0% 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 

分 类 号：TL351.1[核科学技术—核技术及应用]