利用TRISO燃料紧凑型压水堆堆芯的概念设计研究
摘要
本文研究的主要目的是在压水堆中使用TRISO燃料并进行紧凑型反应堆设计。由于TRISO燃料良好的防止裂变碎片逸出的能力,所以被当今反应堆设计研究所青睐。当前的研究集中于通过对设计堆芯的物理和稳态热工水力分析,验证在不采用PWR中常用的反应性补偿措施情况下,使用TRISO燃料PWR技术的可行性。
为了完成反应堆设计工作,必须首先完成设计参数计算工作,确定一些重要的燃料和堆芯设计参数。对于设计完成的堆芯的分析在本文中分三个主要部分进行。首先是过剩反应性控制机理；其次是中子学设计；最后进行堆芯的稳态热工水力分析。基于输运理论的计算程序WIMS-D/4程序,基于扩散理论的CITATION程序和轻水堆瞬态分析程序RELAP5都被应用与本文的概念设计研究中。
在设计中一个最重要的特点是TRISO燃料颗粒新颖的成份,它可以保证在整个燃料循环过程中反应性控制技术的实现。少量5.0 w/o的Pu-240将取代部分U-235加入TRISO燃料中,在恰当数量的控制棒作用下,该TRISO燃料微粒的使用可以不采用可溶硼系统和可燃毒物来补偿剩余反应性。由于无溶解硼(SBF)和无可燃毒物理念可以减小反应堆体积,均匀堆芯燃耗,所以更多的被应用在小型和中型反应堆(SMR)中。这种燃料的一些特性(例如：加热性能、脱盐性能和限制功率产生的性能)可以使得设计的堆芯能在比一般的PWR堆芯更低的温度和压力下运行。反应堆的功率密度也会相应的降低,TRISO燃料的使用可以保障堆芯在所有的工况下安全运行。
本文的结果说明将TRISO燃料和PWR技术的结合可以得到更可行、安全的核电设计。使用少量5.0w／o的Pu-240在TRISO燃料微粒中,燃料可以在整个循环过程中显著的减少剩余反应性。在燃料的寿期初,剩余反应性从27%△k/k降到6.22%△k/k,设计中可以不再使用硼溶液系统和可燃毒物。多普勒效应、慢化剂和空泡份额数分别为-3.34 pcm K-(?)、-4.90 pcm K-1和-91.00 pcm％VM-(?)
本文的稳态热工水力分析结果说明在额定工况和115%工况下MDNBR比-般PWR更大。设计堆芯的燃料芯部运行温度仅为9300C,低于UO2的熔化温度和一般PWR的燃料中心温度。在整个燃料循环中最大功率的峰值因子仅为2.10,局部的功率因子(LPF)小于2.15。在使用260 kg重金属燃料情况下,反应堆堆芯寿期可达550 EFPD。
The aim of this research is to design a compact nuclear reactor by utilizing TRISO fuel in PWR technology. TRISO fuel has been chosen for the current design study because of its superior reliability against the release of fission fragments. The study is focused on the neutronics and steady state thermal hydraulic safety analysis of the designed core to assess the feasibility of utilizing TRISO fuel in PWR technology without any modification in existing PWR design.
To accomplish the task a detailed parametric study was carried out to identify the important fuel and core design parameters as a starting point for a complete reactor core design. The designed core was analyzed in the dissertation which comprises of 3 main domains. First is the development of excess reactivity control mechanism. Second is the neutronics design and finally, the steady state thermal hydraulic analysis of the designed core. Transport theory lattice simulation code WIMS-D/4. diffusion theory based computer code CITATION and light water reactor transient analysis code RELAP5 were used for the conceptual design study.
An important feature of the design is a novel TRISO fuel particle composition which provides reactivity control technique over the entire fuel cycle. A small amount of Pu-240 with 5.0 w/o has been added in TRISO fuel particle in the place of U-238. The utilization of inventive TRISO fuel particle can completely eliminate the use of soluble boron system and requirement of burnable poison if adequate number of control rods is used. The Soluble Boron Free (SBF) and Burnable Poison Free (BPF) concepts are more viable in small and medium size reactors (SMRs) because it makes the plant simpler and uniform burnup can be achieved throughout the core. The designed core operates at lower temperature and pressure than a standard PWR power reactor because of its specific use (i.e. heating, desalination and limited power production). The reactor power density is also relatively low and the presence of TRISO fuel also ensures further safety under all operating scenarios.
The research presented in the thesis revealed that the combination of TRISO fuel in PWR technology results in a more reliable, safer and better nuclear design. The use of small amount of Pu-240 with 5.0 w/o in TRISO fuel particle resulted in a significant reduction of the excess reactivity through out the fuel cycle. The excess reactivity was reduced to only 6.22%Δk/k from 27.00%Δk/k at the start of fuel cycle. The soluble boron system and burnable poison has been completely eliminated from the design due to the enhanced reactivity control of the design. The values of Doppler, moderator and void reactivity coefficients were found-3.34 pcm K-1,-4.90 pcm K-1 and-91.00 pcm%VM-1 respectively.
Steady state thermal hydraulic analysis presented in this thesis depicted that the value of minimum departure from nucleate boiling ratio (MDNBR) at rated power and 115%power is sufficiently larger than the nominal value PWR design. The fuel centre line operating temperature of the designed core was only 930℃which is well below than the melting temperature of UO2 and centerline fuel temperature of standard PWR design. It was also observed that the maximum value of total power peaking factor was only 2.10 and the local power peaking factor (LPF) remained less than 2.15 throughout the fuel cycle. The reactor remains critical for at least 550 EFPD with 260 kg of heavy metal fuel inventory.
为了完成反应堆设计工作,必须首先完成设计参数计算工作,确定一些重要的燃料和堆芯设计参数。对于设计完成的堆芯的分析在本文中分三个主要部分进行。首先是过剩反应性控制机理；其次是中子学设计；最后进行堆芯的稳态热工水力分析。基于输运理论的计算程序WIMS-D/4程序,基于扩散理论的CITATION程序和轻水堆瞬态分析程序RELAP5都被应用与本文的概念设计研究中。
在设计中一个最重要的特点是TRISO燃料颗粒新颖的成份,它可以保证在整个燃料循环过程中反应性控制技术的实现。少量5.0 w/o的Pu-240将取代部分U-235加入TRISO燃料中,在恰当数量的控制棒作用下,该TRISO燃料微粒的使用可以不采用可溶硼系统和可燃毒物来补偿剩余反应性。由于无溶解硼(SBF)和无可燃毒物理念可以减小反应堆体积,均匀堆芯燃耗,所以更多的被应用在小型和中型反应堆(SMR)中。这种燃料的一些特性(例如：加热性能、脱盐性能和限制功率产生的性能)可以使得设计的堆芯能在比一般的PWR堆芯更低的温度和压力下运行。反应堆的功率密度也会相应的降低,TRISO燃料的使用可以保障堆芯在所有的工况下安全运行。
本文的结果说明将TRISO燃料和PWR技术的结合可以得到更可行、安全的核电设计。使用少量5.0w／o的Pu-240在TRISO燃料微粒中,燃料可以在整个循环过程中显著的减少剩余反应性。在燃料的寿期初,剩余反应性从27%△k/k降到6.22%△k/k,设计中可以不再使用硼溶液系统和可燃毒物。多普勒效应、慢化剂和空泡份额数分别为-3.34 pcm K-(?)、-4.90 pcm K-1和-91.00 pcm％VM-(?)
本文的稳态热工水力分析结果说明在额定工况和115%工况下MDNBR比-般PWR更大。设计堆芯的燃料芯部运行温度仅为9300C,低于UO2的熔化温度和一般PWR的燃料中心温度。在整个燃料循环中最大功率的峰值因子仅为2.10,局部的功率因子(LPF)小于2.15。在使用260 kg重金属燃料情况下,反应堆堆芯寿期可达550 EFPD。
The aim of this research is to design a compact nuclear reactor by utilizing TRISO fuel in PWR technology. TRISO fuel has been chosen for the current design study because of its superior reliability against the release of fission fragments. The study is focused on the neutronics and steady state thermal hydraulic safety analysis of the designed core to assess the feasibility of utilizing TRISO fuel in PWR technology without any modification in existing PWR design.
To accomplish the task a detailed parametric study was carried out to identify the important fuel and core design parameters as a starting point for a complete reactor core design. The designed core was analyzed in the dissertation which comprises of 3 main domains. First is the development of excess reactivity control mechanism. Second is the neutronics design and finally, the steady state thermal hydraulic analysis of the designed core. Transport theory lattice simulation code WIMS-D/4. diffusion theory based computer code CITATION and light water reactor transient analysis code RELAP5 were used for the conceptual design study.
An important feature of the design is a novel TRISO fuel particle composition which provides reactivity control technique over the entire fuel cycle. A small amount of Pu-240 with 5.0 w/o has been added in TRISO fuel particle in the place of U-238. The utilization of inventive TRISO fuel particle can completely eliminate the use of soluble boron system and requirement of burnable poison if adequate number of control rods is used. The Soluble Boron Free (SBF) and Burnable Poison Free (BPF) concepts are more viable in small and medium size reactors (SMRs) because it makes the plant simpler and uniform burnup can be achieved throughout the core. The designed core operates at lower temperature and pressure than a standard PWR power reactor because of its specific use (i.e. heating, desalination and limited power production). The reactor power density is also relatively low and the presence of TRISO fuel also ensures further safety under all operating scenarios.
The research presented in the thesis revealed that the combination of TRISO fuel in PWR technology results in a more reliable, safer and better nuclear design. The use of small amount of Pu-240 with 5.0 w/o in TRISO fuel particle resulted in a significant reduction of the excess reactivity through out the fuel cycle. The excess reactivity was reduced to only 6.22%Δk/k from 27.00%Δk/k at the start of fuel cycle. The soluble boron system and burnable poison has been completely eliminated from the design due to the enhanced reactivity control of the design. The values of Doppler, moderator and void reactivity coefficients were found-3.34 pcm K-1,-4.90 pcm K-1 and-91.00 pcm%VM-1 respectively.
Steady state thermal hydraulic analysis presented in this thesis depicted that the value of minimum departure from nucleate boiling ratio (MDNBR) at rated power and 115%power is sufficiently larger than the nominal value PWR design. The fuel centre line operating temperature of the designed core was only 930℃which is well below than the melting temperature of UO2 and centerline fuel temperature of standard PWR design. It was also observed that the maximum value of total power peaking factor was only 2.10 and the local power peaking factor (LPF) remained less than 2.15 throughout the fuel cycle. The reactor remains critical for at least 550 EFPD with 260 kg of heavy metal fuel inventory.
引文
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