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混合能源堆包层中子学初步概念设计 被引量:16

Preliminary Concept Design on Blanket Neutronics of a Fusion-Fission Hybrid Reactor for Energy Production
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摘要 提出了以天然铀或压水堆乏燃料的锆合金为燃料、轻水冷却、后处理铀钚不分离、具有良好防核扩散性能的能源堆概念。利用MCNP程序与ORIGENS程序相耦合的方法设计了包层中子学初步方案,给出了初步换料方案。能源堆对聚变堆芯参数的要求不高于国际热核聚变实验堆(ITER),可以实现利用^(238)U的目的。 A concept of energy production reactor is given in this paper. It uses the natural uranium or U-Zr alloy of the spent fuel in PWR as its fuel and cooled by water. This concept is proliferation resistant for it needs no separation of plutonium from spent fuel. Preliminary concept design on blanket neutronics is finished by a burnup code coupled by MCNP and ORIGENS. Designs with natural uranium or spent fuel from PWR as fuels are computed and preliminary reload scheme is given. It requires lower fusion power than ITER and makes full use of ^238U, which is of great significance for the sustainable development of nuclear energy.
出处 《核动力工程》 EI CAS CSCD 北大核心 2010年第4期5-7,20,共4页 Nuclear Power Engineering
关键词 混合堆 铀锆合金 轻水 MCNP程序 ORIGENS程序 Hybrid reactor, U-Zr alloy, Light water, MCNP code, ORIGENS code
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