钍基熔盐堆中子能谱测量方法的研究
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摘要
中子能谱对于核工程、核物理及核实验的研究工作有重要的意义，特别是对于新型堆的设计和建造，中子能谱的测量可为堆参数设计的合理性提供参考。本文采用理论与实验相结合的方法，重点就如何提高活化法测量中子能谱的精度及实验中所涉及的相关问题作了深入研究，为测量钍基熔盐堆内特殊环境下的中子能谱提供测量方案。
本论文共分为八个部分，第一部分为引言，主要介绍钍基熔盐堆建造的背景及中子能谱测量对新型堆-钍基熔盐堆的意义；第二部分为中子能谱的理论计算方法，从中子输运方程着手，阐述了确定论方法和蒙特卡罗法的基本原理及其发展和应用，将两种方法的优缺点进行比较，结合本研究的需要，选用基于蒙特卡罗思想的MCNP计算程序作为本文中子能谱理论模拟计算的主要工具；第三部分为中子能谱的测量方法，从中子的特性开始，研究探测中子的原理，根据中子与物质作用的基本原理，结合不同中子源类型及中子场的特点，逐步介绍各种中子能谱测量的方法，综合考虑决定采用活化法测量中子能谱；第四部分为活化法测量中子能谱，首先从理论计算与实验测定两方面介绍活化法测量中子能谱的基本原理，然后介绍解谱的方法及解谱程序，详细分析了解谱程序SAND-Ⅱ和MSIT的解谱原理及解谱过程，研究了解谱中所需的群截面受箔片厚度和温度的影响；第五部分为对活化材料和高纯锗探测器的研究，这一部分为采用活化法测量中子能谱实验前的准备工作，通过大量调研、总结，介绍了活化材料的选取原则及活化箔的制备原则，分析了影响探测效率的主要因素，通过模拟计算比较了点源与面源对高纯锗探测效率的影响及源的自吸收问题；第六部分为活化法测量中子能谱的实验验证，利用活化法分别测量了西安脉冲堆辐照腔及原型微堆辐照孔道内的中子能谱，利用解谱程序SAND-Ⅱ和MSIT进行解谱，利用蒙特卡罗对解谱结果的不确定度进行分析，探讨了初始输入谱对于解谱结果的影响，分析了整个实验过程中可能出现的误差，将解谱结果与前人的实验结果进行比较，二者基本一致；第七部分为拟建钍基熔盐堆(TMSR-SF1)内中子能谱的理论计算及测量方案，TMSR-SF1是一个以液态熔盐为冷却剂，燃料元件为固态球型的实验堆，由于其在2MW功率正常运行时，反射层与堆内温度达550oC～650oC，这样的高温测量环境对中子能谱的测量技术有很大的考验，本部分通过对耐高温“兔盒”的研制及耐高温活化箔的选取、制备等，给出高温环境下测量中子能谱的方案；第八部分为结论与展望，归纳了本文所研究的主要内容，指出下一步的主要工作及工作设想。
本论文采用理论计算与实验测量相结合的方法，掌握了测量环境温度不高于100oC的活化法测量中子能谱的关键技术，为拟测高温环境下的中子能谱打下基础。
The neutron energy spectrum is very important to the nuclear engineering design andapplication, as well as to the nuclear physics research. For a new type of reactor，the thoriummolten salt reactor, the neutron energy spectrum can provide a reference to the rationality of thedesign parameters. This thesis focuses on how to improve the measuring accuracy of the neutronenergy spectrum by activation method considering the related issues involved in experiments, inaddition to the measurement scheme of the neutron energy spectrum under the specificenvironment in the thorium molten salt reactor.
The thesis is divided into eight parts. The first part mainly introduces the background of thethorium molten salt reactor and the significance of the neutron energy spectrum measurement tothe thorium molten salt reactor. In the second part, the theoretical calculation method of theneutron energy spectrum is researched. It is found that MCNP, based on Monte Carlo, can be asthe main tool to simulate the neutron energy spectrum after comparing the two methods,deterministic method and Monte Carlo method. In the third part, the measurement methods ofneutron energy spectrum are presented. The activation method is adopted by analyzing,considering the detecting principle of the neutron and the different measurement methods ofneutron energy spectrum. The fourth part briefly shows the activation method of neutron energyspectrum measurement, including the fundamental of the theoretical calculation andexperimental measurement，the methods of spectrum unfolding, the principle and process ofspectrum unfolding for SAND-Ⅱand MSIT, and the group cross-section affected by thethickness of the foil and the temperature of environment. In the fifth part, the active material andhigh purity germanium detector are researched, as the preparation work of the using activationmethod to measure the neutron energy spectrum. The selecting principle of active material andthe preparation principle of activation foil are stated. The main influence factors of the detectionefficiency are studied according to the shape and the absorptiong of the source. The sixth part isexperimental verification. The neutron energy spectrum in the radiation cavity of Xi’An pulsedreactor and prototype micro reactor is respectively measured by the activation method, choosingSAND-Ⅱand MSIT to unfold the spectrum. The uncertainty of the result is analysed using theMonte Carlo method, and the influence of initial input spectrum on the results is discussed. In the seventh part, the schemes for the theoretical simulation and the measurement of the neutronenergy spectrum for a proposed experiment reactor，the thorium molten salt reactor-solid facility(TMSR-SF1) are given, especially in the high temperature conditions when it is550oC～650oCin the reflector，along with the core, during TMSR-SF1normal working. The eighth part gives abriefly summary and prospect.
In this thesis, the measurement of neutron energy spectrum in TMSR-SF1is studied, as wellas master the key measurement technology of neutron energy spectrum using activation methodwhen the temperature of environment is not higher than100oC.
本论文共分为八个部分，第一部分为引言，主要介绍钍基熔盐堆建造的背景及中子能谱测量对新型堆-钍基熔盐堆的意义；第二部分为中子能谱的理论计算方法，从中子输运方程着手，阐述了确定论方法和蒙特卡罗法的基本原理及其发展和应用，将两种方法的优缺点进行比较，结合本研究的需要，选用基于蒙特卡罗思想的MCNP计算程序作为本文中子能谱理论模拟计算的主要工具；第三部分为中子能谱的测量方法，从中子的特性开始，研究探测中子的原理，根据中子与物质作用的基本原理，结合不同中子源类型及中子场的特点，逐步介绍各种中子能谱测量的方法，综合考虑决定采用活化法测量中子能谱；第四部分为活化法测量中子能谱，首先从理论计算与实验测定两方面介绍活化法测量中子能谱的基本原理，然后介绍解谱的方法及解谱程序，详细分析了解谱程序SAND-Ⅱ和MSIT的解谱原理及解谱过程，研究了解谱中所需的群截面受箔片厚度和温度的影响；第五部分为对活化材料和高纯锗探测器的研究，这一部分为采用活化法测量中子能谱实验前的准备工作，通过大量调研、总结，介绍了活化材料的选取原则及活化箔的制备原则，分析了影响探测效率的主要因素，通过模拟计算比较了点源与面源对高纯锗探测效率的影响及源的自吸收问题；第六部分为活化法测量中子能谱的实验验证，利用活化法分别测量了西安脉冲堆辐照腔及原型微堆辐照孔道内的中子能谱，利用解谱程序SAND-Ⅱ和MSIT进行解谱，利用蒙特卡罗对解谱结果的不确定度进行分析，探讨了初始输入谱对于解谱结果的影响，分析了整个实验过程中可能出现的误差，将解谱结果与前人的实验结果进行比较，二者基本一致；第七部分为拟建钍基熔盐堆(TMSR-SF1)内中子能谱的理论计算及测量方案，TMSR-SF1是一个以液态熔盐为冷却剂，燃料元件为固态球型的实验堆，由于其在2MW功率正常运行时，反射层与堆内温度达550oC～650oC，这样的高温测量环境对中子能谱的测量技术有很大的考验，本部分通过对耐高温“兔盒”的研制及耐高温活化箔的选取、制备等，给出高温环境下测量中子能谱的方案；第八部分为结论与展望，归纳了本文所研究的主要内容，指出下一步的主要工作及工作设想。
本论文采用理论计算与实验测量相结合的方法，掌握了测量环境温度不高于100oC的活化法测量中子能谱的关键技术，为拟测高温环境下的中子能谱打下基础。
The neutron energy spectrum is very important to the nuclear engineering design andapplication, as well as to the nuclear physics research. For a new type of reactor，the thoriummolten salt reactor, the neutron energy spectrum can provide a reference to the rationality of thedesign parameters. This thesis focuses on how to improve the measuring accuracy of the neutronenergy spectrum by activation method considering the related issues involved in experiments, inaddition to the measurement scheme of the neutron energy spectrum under the specificenvironment in the thorium molten salt reactor.
The thesis is divided into eight parts. The first part mainly introduces the background of thethorium molten salt reactor and the significance of the neutron energy spectrum measurement tothe thorium molten salt reactor. In the second part, the theoretical calculation method of theneutron energy spectrum is researched. It is found that MCNP, based on Monte Carlo, can be asthe main tool to simulate the neutron energy spectrum after comparing the two methods,deterministic method and Monte Carlo method. In the third part, the measurement methods ofneutron energy spectrum are presented. The activation method is adopted by analyzing,considering the detecting principle of the neutron and the different measurement methods ofneutron energy spectrum. The fourth part briefly shows the activation method of neutron energyspectrum measurement, including the fundamental of the theoretical calculation andexperimental measurement，the methods of spectrum unfolding, the principle and process ofspectrum unfolding for SAND-Ⅱand MSIT, and the group cross-section affected by thethickness of the foil and the temperature of environment. In the fifth part, the active material andhigh purity germanium detector are researched, as the preparation work of the using activationmethod to measure the neutron energy spectrum. The selecting principle of active material andthe preparation principle of activation foil are stated. The main influence factors of the detectionefficiency are studied according to the shape and the absorptiong of the source. The sixth part isexperimental verification. The neutron energy spectrum in the radiation cavity of Xi’An pulsedreactor and prototype micro reactor is respectively measured by the activation method, choosingSAND-Ⅱand MSIT to unfold the spectrum. The uncertainty of the result is analysed using theMonte Carlo method, and the influence of initial input spectrum on the results is discussed. In the seventh part, the schemes for the theoretical simulation and the measurement of the neutronenergy spectrum for a proposed experiment reactor，the thorium molten salt reactor-solid facility(TMSR-SF1) are given, especially in the high temperature conditions when it is550oC～650oCin the reflector，along with the core, during TMSR-SF1normal working. The eighth part gives abriefly summary and prospect.
In this thesis, the measurement of neutron energy spectrum in TMSR-SF1is studied, as wellas master the key measurement technology of neutron energy spectrum using activation methodwhen the temperature of environment is not higher than100oC.
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