IFBA/WABA可燃毒物元件的燃耗特性分析

针对AP1000反应堆采用的燃料元件表面涂硼毒物(IFBA)和湿式环状可燃毒物棒(WABA),分别采用蒙卡程序MCNP5和组件均匀化计算程序CASMO构建含可燃毒物的燃料组件计算模型,基于MCNP5分析了可燃毒物棒布置方式及数目对组件初始k_(inf)、局部功率分布的影响;基于CASMO分析了不同类型可燃毒物组件的燃耗特性。结果表明:在燃料表面涂硼作为可燃毒物具有良好的燃耗跟踪特性,燃耗寿期内k_(inf)变化较小且几乎没有残留;同时将含IFBA毒物燃料元件交叉布置可获得较小的组件初始k_(inf)值,并能更好地展平组件局部功率分布,但随IFBA涂层变厚,组件k_(inf)的变化率逐渐变小,但温度系数绝对值呈上升趋势。     

PWR堆芯中弥散型可燃毒物的燃耗特性研究

在压水反应堆(PWR)堆芯核设计中,通常采用可燃毒物来补偿反应性和展平功率分布。对于长寿期堆芯设计,可燃毒物的消耗和燃料燃耗的匹配研究更为重要。利用基于蒙特卡罗方法开发的堆芯燃耗计算程序(MOI)对天然元素、人工核素、可溶硼等多种弥散型可燃毒物进行燃耗特性分析。结果表明锕系可燃核素231Pa、240Pu等弥散型可燃毒物可用于长寿期PWR的设计。     

可燃毒物提高小型压水堆堆芯寿期研究

针对长寿期堆芯的应用需求,开展了提高小型压水堆堆芯寿期研究。以棒状燃料为对象,对不同栅格尺寸和不同可燃毒物的选取进行计算,得出小型压水堆堆芯寿期相关影响因素。通过对不同尺寸的燃料栅格进行输运-燃耗计算,得到燃耗最佳栅格尺寸。以燃耗最佳栅格尺寸建立组件,并选择转换性能好的锕系核素~(240)PuO_2作为可燃毒物,利用~(240)Pu吸收中子转换成易裂变核素~(241)Pu的特性,对堆芯实现反应性控制和寿期延长。本研究通过对燃料栅格尺寸和可燃毒物的合理选择,提高了燃料利用率,达到延长堆芯寿期的目的。     

燃耗信任制中可燃毒物对乏燃料反应性的影响分析

以压水堆(PWR)常用的可燃毒物棒(BPRs)为研究对象,定性分析了组件燃耗过程中不同类型的BPRs对燃料组件反应性的影响,为基于燃耗信任制的乏燃料贮存系统临界安全分析保守参数的选取提供参考。分析表明,在组件燃耗过程中含有BPRs时,忽略含钆毒物可使临界分析结果保守,而必须考虑涂硼燃料元件(IFBA)、湿式环状可燃毒物棒(WABA)、硼玻璃可燃毒物棒(PYREX)等对乏燃料反应性的影响。     

锕系可燃毒物板状燃料组件燃耗特性研究

为研究锕系可燃毒物在板状燃料组件的燃耗特性和延长寿期的适用性，本研究以不同富集度的板状燃料为对象，计算分析了相同初始组件无限增殖因数（kinf）情况下的锕系可燃毒物装载量、燃耗深度、235U利用率等。结果表明，在低富集度（4%~7%）情况下，240Pu可燃毒物在寿期内表现出较好的转换效应，235U利用率高，可起到延长堆芯寿期的作用；在中等富集度（25%~40%）情况下，240Pu可燃毒物的转换效应减弱，而231Pa可燃毒物表现出较好的转换效应；在高富集度（70%~97%）情况下， 231Pa可燃毒物的转换效应减弱，但含231Pa组件的235U利用率和达到的燃耗深度在所选锕系核素中最大；240Pu可作为长寿期低富集度燃料可燃毒物的选择，231Pa可作为长寿期中等、高富集度燃料可燃毒物的选择。      

长寿期压水堆颗粒弥散可燃毒物中子学设计与分析

为实现长寿期压水堆的低硼运行,对颗粒弥散可燃毒物进行了中子学设计与分析,颗粒弥散可燃毒物的自屏效应可通过颗粒半径进行调节,能实现可燃毒物消耗和燃料燃耗的较优匹配。本文选取目前压水堆常用的快燃耗可燃毒物B、Gd为对象,研究了颗粒弥散可燃毒物不同颗粒半径和填充份额对组件中子学特性的影响。结果表明,颗粒弥散可燃毒物能实现长期稳定的反应性控制,其中BISO含硼弥散颗粒符合长寿期压水堆低硼运行的要求,适合作为长寿期压水堆的候选可燃毒物进行下一步研究。     

长寿期压水堆板状燃料组件可燃毒物选型研究

可燃毒物在长寿期压水堆中起着至关重要的作用,板状燃料组件在长寿期压水堆中具有较好的应用前景。本文开展长寿期压水堆板状燃料组件可燃毒物选型及中子学特性研究,对含不同可燃毒物的板状燃料组件进行输运-燃耗计算,筛选出中子学性能较好的可燃毒物。结果表明,采用富集同位素157Gd、167Er和B4C作为可燃毒物时,几乎无反应性惩罚;当采用PACS-J和231Pa作为可燃毒物时,因其自身特性,在寿期末不仅未造成反应性惩罚,且延长了组件寿期,提高了燃料利用率;PACS-J与慢燃耗可燃毒物组合,可获得更优的反应性曲线。由本文结果可知,板状燃料组件可以选用富集同位素157Gd、富集同位素167Er、B4C、231Pa和PACS-J作为可燃毒物,可燃毒物组合可以选用PACS-Er和PACS-Pa两种组合方案。     

百万千瓦级压水堆核电站长燃耗堆芯钆可燃毒物优化研究

对百万千瓦级参考核电站长燃耗堆芯（１８个月换料）采用的可燃毒物（钆）含量与堆芯燃料管理主要结果进行了分析研究。该研究采用先进的燃料管理程序系统,对不同可燃毒物含量和不同可燃毒物棒根数的燃料组件进行了计算,给出了组件无限增殖因子（ｋｉｎｆ）随燃耗的变化关系,据此对参考堆芯采用相同的装载进行了４种方案燃料管理计算。计算结果表明,对于堆芯燃料管理,采用低可燃毒物含量、含可燃毒物棒数多的装载方案明显优于高可燃毒物含量、含可燃毒物棒少的堆芯装载方案。     

可燃毒物提高小型压水堆堆芯寿期研究

针对长寿期堆芯的应用需求,开展了提高小型压水堆堆芯寿期研究。以棒状燃料为对象,对不同栅格尺寸和不同可燃毒物的选取进行计算,得出小型压水堆堆芯寿期相关影响因素。通过对不同尺寸的燃料栅格进行输运 燃耗计算,得到燃耗最佳栅格尺寸。以燃耗最佳栅格尺寸建立组件,并选择转换性能好的锕系核素²⁴⁰PuO₂作为可燃毒物,利用²⁴⁰Pu吸收中子转换成易裂变核素²⁴¹Pu的特性,对堆芯实现反应性控制和寿期延长。本研究通过对燃料栅格尺寸和可燃毒物的合理选择,提高了燃料利用率,达到延长堆芯寿期的目的。     

百万千瓦级压水堆核电站长燃烧堆芯钆可燃毒物优化研究

对百万千瓦参考核电站长燃耗堆芯采用的可燃毒物含量与堆芯燃料管理主要结果进行分析研究。该研究采用先进的燃料管理程序系统，对不同可燃毒物含量和不同可燃毒物棒根数据的进行了计算，给出了组件无了增殖因子随燃耗的变化关系，据此对参考堆芯采用相同的装载进行了４种方案燃料管理计算。     

颗粒可燃毒物空间自屏效应分析研究

可燃毒物被布置于反应堆堆芯中以控制堆芯剩余反应性,颗粒可燃毒物由于空间自屏效应而具有区别于常规均匀弥散可燃毒物的特性,同时颗粒可燃毒物可以增加可燃毒物的使用自由度,通过调整可燃毒物类型、可燃毒物颗粒尺寸以及可燃毒物体积份额以实现堆芯反应性的长期和平稳控制。本文重点研究颗粒可燃毒物的颗粒尺寸对系统反应性以及颗粒内有效核素核子密度变化规律的影响,并解释颗粒可燃毒物由于空间自屏效应而产生的"洋葱"效应,同时对比分析了多种常见可燃毒物不同颗粒尺寸下的中子学规律,对颗粒可燃毒物用于堆芯反应性控制具有重要的指导意义。     

Reactor physics ideas for large scale utilization of thorium in gas cooled reactors

The physics principles for maximizing the fertile to fissile conversion were used in developing reactor concepts for large scale utilization of thorium in thermal and fast reactors (Jagannathan & Pal, 2006; Jagannathan et al., 2008). It is recognized that these principles are very well suited for ‘He’ gas cooled reactors with graphite moderator since both helium gas coolant and the graphite moderator have low neutron absorption characteristics and thus gives better neutron economy. In this paper, these ideas are applied to the High Temperature Test Reactor (HTTR) core of Japan to assess its advantage over the present day gas cooled reactors. HTTR is helium cooled and graphite moderated system. Significant amount of thorium has been loaded in the HTTR core with some minimal changes in the existing core design. The modified design is called HTTR-M core.In the HTTR-M core, the fuel is changed from enriched UO₂ fuel to Pu in ThO₂ fuel. The locations of boron type burnable poison rods within each fuel assembly of HTTR are replaced by one cycle irradiated thoria rods. Also, the B₄C type control assembly around the HTTR core is replaced by fresh seedless thorium assembly. The fertile thoria assembly are scattered uniformly in the HTTR-M core. The equilibrium core of HTTR-M shows very small burnup reactivity swing. The core excess reactivity is ∼18 mk at BOC and reduces to 1 mk at 660 days. It is interesting to note that this small reactivity change is intrinsically achieved by the choice of seed and fertile dimensions and their contents without the use of burnable poison rods or mechanical control rods which are used in HTTR core. The burnup reactivity swing in the latter after using burnable poison is ∼100 mk. The fissile seed inventory ratio (FIR) in a fuel cycle is 0.90 as compared with 0.717 of HTTR core. Since ²³³U is a better fissile nuclide with highest ‘η’ value in thermal range, the above conversion ratio can be regarded as quite good.     

用于燃耗计算的三维MCCOOR程序系统

介绍了由标准程序MCNP、COUPLE、ORIGEN-S组成的耦合程序系统MCCOOR的结构和功能,用VVER等轻水堆栅元和燃料组件的多个Benchmark模型进行了检验.本文列举了在VVER-1000带可燃毒物Gd的燃料组件Benchmark模型上,分别用UO2和MOX燃料的检验结果.所有检验结果表明:MCCOOR的反应性和核素成分的计算结果与Benchmark的结果在误差范围内一致.     

CPWR640堆芯核设计

中国６００ＭＷ核电机组ＣＰＷＲ６４０先进反应堆的特点是采用先进燃料组件,低功率密度堆芯,长循环低泄漏燃料管理方式,由钆可燃毒物补偿堆芯后备反应性,本文介绍了ＣＰＷＲ６４０反应堆的核设计准则,堆芯特性与主要参数,并给出了堆芯核设计的主要计算机程序,计算结果及分析。     

Simulation study on candle burnup applied to block-type high temperature gas cooled reactor

The CANDLE burnup is a new reactor burnup concept, where the distributions of fuel nuclide densities, neutron flux, and power density move with the same constant speed along the core axis from bottom to top (or from top to bottom) of the core and without any change in their shapes. It can be applied easily to a block-type high temperature gas cooled reactor (HTGR) using an appropriate burnable poison with a high neutron absorption cross section mixed with uranium oxide fuel. In this study, natural gadolinium is used as burnable poison. In the present paper, the simulation of the burnup for the steady state and the startup is performed.

For the steady state simulation with direct solutions of steady state nuclide densities as inputs, the difference between the results of the steady state analysis and the simulation analysis is very small. It confirms that the steady state analysis is correct. When the initial core is constructed from easily available nuclides, the simulation result gives a reactivity change of 1.7% at a burnup time of 0.7 years.     

A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control

In high temperature reactors, burnable absorbers are utilized to manage the excess reactivity at the early stage of the fuel cycle. In this paper QUADRISO particles are proposed to manage the initial excess reactivity of high temperature reactors. The QUADRISO concept synergistically couples the decrease of the burnable poison with the decrease of the fissile materials at the fuel particle level. This mechanism is set up by introducing a burnable poison layer around the fuel kernel in ordinary TRISO particles or by mixing the burnable poison with any of the TRISO coated layers. At the beginning of life, the initial excess reactivity is small because some neutrons are absorbed in the burnable poison and they are prevented from entering the fuel kernel. At the end of life, when the absorber is almost depleted, more neutrons stream into the fuel kernel of QUADRISO particles causing fission reactions. The mechanism has been applied to a prismatic high temperature reactor with europium or erbium burnable absorbers, showing a significant reduction in the initial excess reactivity of the core.     

A study on improvement of sodium cooled TRU burner design using burnable poison

A new design approach to improve safety characteristics of sodium cooled core for transuranic element transmutation is discussed. In the new option, some amount of fertile material is removed for reduction of sodium void reactivity. Simultaneously, a burnable absorber material is loaded in replacement of fertile material to compensate for reactivity drop during the fuel depletion. Two methods of burnable absorber loading are considered such as the homogeneous and the heterogeneous. In the results, it is found that the homogeneous loading cannot reduce the sodium void reactivity but makes the reactivity more positive. On the other hand, the heterogeneous loading can reduce the sodium void reactivity successfully. It is also found that the increment in burnup reactivity swing is negligible when the burnable poison is heterogeneously loaded. It is concluded that if the burnable poison material is loaded appropriately, the sodium void reactivity can be reduced without any significant penalty of increase in burnup reactivity swing.