ADS嬗变堆中的冷却剂选择及具有温度反馈的系统仿真研究
发布时间:2018-03-23 04:20
本文选题:MCNP5 切入点:ADS 出处:《东华理工大学》2014年硕士论文 论文类型:学位论文
【摘要】:加速器驱动次临界系统(简称ADS)是嬗变核废料的最强有力工具,ADS利用加速器加速的高能质子与重靶核发生散裂反应,用散裂产生的中子作为中子源来驱动次临界系统,这种处理乏燃料的方式被认为是一条有前途的新一代核能开发的技术路线,其研究成果将明显提高核能系统的资源效益和环境效益。本文结合国内外ADS嬗变堆的研究情况,以及蒙特卡罗方法研究的文献,通过使用ORIGEN2.1和MCNP5软件,研究ADS系统在冷却剂选择、次锕系核素和长寿命裂变产物的积累情况,发现在研究的3种冷却剂中,液态铅影响总体上最大,而液态钠影响最小;通过能谱分析得出99Tc对中子能谱影响较大,而129I对中子能谱的影;再通过Simulink软件对嬗变堆的反应性变化做了研究,发现反应堆在有外部反应性引入的情况下,功率被稳定在另一个功率水平上。由温度效应引入的负的反应性,使反应堆具有自稳性。得到的结论为ADS的后续研究提供参考。
[Abstract]:Accelerator driven subcritical system (ads) is the most powerful tool for transmutation of nuclear waste. Ads uses accelerator accelerated high energy proton to spallate with heavy target nucleus, and uses neutron produced by spallation as neutron source to drive subcritical system. This treatment of spent fuel is considered to be a promising technical route for the development of new generation nuclear energy, and its research results will obviously improve the resource and environmental benefits of nuclear energy system. This paper combines the research situation of ADS transmutation reactor at home and abroad. Through the use of ORIGEN2.1 and MCNP5 software, the paper studies the selection of coolant, the accumulation of minor actinide nuclides and long-lived fission products in the system of ADS, and finds out that in the three coolants studied, The influence of liquid lead on the whole is the greatest, while the influence of liquid sodium is the least. By energy spectrum analysis, it is concluded that 99Tc has a great influence on neutron energy spectrum, while 129I has a great effect on neutron energy spectrum. The reactivity changes of transmutation reactor are studied by Simulink software. It is found that when the reactor is introduced with external reactivity, the power is stabilized at another power level. The negative reactivity introduced by the temperature effect makes the reactor self-stable. The conclusion provides a reference for the further study of ADS.
【学位授予单位】:东华理工大学
【学位级别】:硕士
【学位授予年份】:2014
【分类号】:TM623;TL24
【参考文献】
相关期刊论文 前1条
1 杨永伟,李浩泉,经荥清;加速器驱动系统的燃料选择[J];原子能科学技术;2005年02期
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