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。     

弥散燃料与可燃毒物双重非均匀性分析

采用传统均匀打混模型计算具有双重非均匀性的弥散燃料或可燃毒物会带来一定的计算偏差。从双重非均匀处理判定公式出发,分析弥散燃料或可燃毒物均匀打混模型计算偏差与各因素的关系,指出针对较高富集度或较大颗粒尺寸的燃料,以及相对较大尺寸可燃毒物颗粒,采用传统均匀打混模型会带来较大的计算偏差。RPT方法可以用来处理弥散燃料以及吸收截面不太大的可燃毒物,但对于硼和钆等吸收截面较大的毒物,RPT方法也会带来较大的计算偏差,同时对新型RPT方法进行了初步探索,虽依然不适用强吸收可燃毒物颗粒,但可以为RPT方法向强吸收体可燃毒物扩展提供思路和借鉴。     

弥散颗粒对中子学计算影响的初步分析

弥散颗粒燃料是一种先进的燃料元件形式,双重非均匀性是它的固有特性。本文基于弥散型燃料,使用MCNP程序对不同燃料颗粒直径、燃料富集度、燃料相体积、可燃毒物颗粒直径和可燃毒物类型的板栅元进行了分析,研究了双重非均匀性对中子学计算的影响,指出双重非均匀性在一定的尺寸下,对于纯燃料芯体板栅元影响较小,对含有弥散可燃毒物的板栅元影响较大,在反应性计算、临界安全分析时必须加以考虑。     

双重非均匀系统环形RPT计算方法研究

弥散燃料与弥散可燃毒物由于具有双重非均匀性,采用传统体积均匀化方法(VHM)会带来较大的计算偏差。反应性等效物理转换(RPT)方法被应用于含弥散燃料的双重非均匀系统,具有方法简单且计算精度较高的特点。本文首先对传统RPT方法和改进RPT(IRPT)方法进行了分析和验证,结果表明,这2种方法对于含有弥散可燃毒物的双重非均匀系统燃耗过程中依然存在相对较大的计算偏差;然后提出环形RPT(RRPT)方法和2步环形RPT(TRRPT)方法分别用于处理含单一颗粒类型和含2种颗粒类型的双重非均匀系统,通过含不同类型可燃毒物的算例验证并与蒙卡颗粒模型基准解对比可知,本文提出的RRPT方法和TRRPT方法可用于处理含弥散燃料和弥散可燃毒物的双重非均匀系统,相比传统方法具有更高计算精度和更广适用范围。     

SCWR双排六边形燃料组件物理性能分析

重点考虑组件的均匀慢化和充分慢化性能,兼顾组件的结构和热工因素的影响,提出了超临界水冷堆(SCWR)双排六边形燃料组件概念设计方案。基于优化的双排六边形燃料组件形式,选取可接受的组件结构材料及尺寸,考虑定位材料和控制棒导向管等因素的影响,评价了其物理性能。研究表明,双排六边形燃料组件概念能在均匀慢化和充分慢化之间达到较好的平衡,组件内所有燃料棒采用同一种燃料成分且不含可燃毒物,即可实现局部功率峰值因子小于1.10的设计目标。     

超临界六角形双排燃料组件性能分析

利用物理-热工水力耦合计算程序系统(MCATHAS)分析2种六角形双排超临界燃料组件,充分考虑了超临界水冷堆(SCWR)中冷却剂、慢化剂轴向温度、密度的剧烈变化和功率分布的相互影响。计算结果表明,双排六角形组件具有均匀慢化和充分慢化性能,文中提出的D6-1型组件在仅采用一种燃料成分、不添加可燃毒物的情形下,其径向功率峰值因子低于1.10。另外,研究表明,由于组件间隙具有较大热周和较小流通面积,需要在实际工程应用中增加隔热涂层以降低组件外盒壁的导热率。     

包覆颗粒燃料分布随机性的影响研究

高温气冷堆采用弥散在石墨基体中的包覆颗粒燃料。包覆颗粒在燃料球内的离散分布及燃料球在堆芯内的离散分布共同导致了燃料分布的双重不均匀性,其分布还具有随机性,由此可能对反应堆的某些参数造成影响。建立适当燃料颗粒随机分布的几何模型,并用MCNP对模型进行相关计算,并与规则分布模型相比较,分析了分布的随机性对有效增殖因数的影响。结果显示,燃料颗粒随机分布会使全堆有效增殖因数较规则模型的稍大,两种模型偏差的主要原因在于两种颗粒排列方式在空间和角度分布的不同。     

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。     

基于遗传算法的可燃毒物设计优化方法研究

可燃毒物可补偿寿期初过剩反应性及展平功率分布,因此对堆芯燃料组件设计具有重要意义。目前传统的优化设计主要依靠设计者的主观经验及判断,复杂耗时,其设计效率及可靠性急待改进。本文将多目标并行遗传算法应用于压水堆组件毒物选型优化,以反应性控制、功率分布和不同时期燃耗剩余等为目标,对可燃毒物材料类型、含可燃毒物燃料棒排列方式、毒物含量、轴向分层等决策变量进行优化,研究了遗传算法在燃料组件毒物多目标优化设计中的理论模型及实现方法。同时将遗传算法与蒙特卡罗粒子输运方法有机结合,应用到压水堆燃料组件设计中,得到了组件可燃毒物优化方案。针对二维和三维燃耗计算,分别筛选了13和40种优化方案。计算结果表明：Er2O3用作毒物的综合效果最好;Gd2O3、Eu2O3和Sm2O3的应用需结合堆芯方案开展进一步研究;HfO2和Dy2O3不适合用作可燃毒物。该结果与通过人工搜索优化得到的结论基本一致。同时,三维轴向分层可为优化提供更多可选的材料种类方案,以部分毒物的分层布置方式可减小功率峰因子。本文研究为堆芯燃料/毒物设计提供了先进方法及工具。     

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。     

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.     

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。     

先进聚合物可燃毒物燃耗特性分析

针对当前新提出的先进聚合物材料(PACS),分析聚合物可燃毒物的材料特性与慢化特性,基于秦山核电厂与Crystal River Three两类堆型燃料组件,对比分析采用不同类型可燃毒物材料时组件的燃耗特性。结果表明:聚合物材料的慢化特性随含氢量呈线性变化关系,调节聚合物分子组成可以改变毒物的燃耗特性。相对传统的可燃毒物材料,先进聚合物可燃毒物体现了良好的毒物特性,全寿期具有更低的局部功率峰,在燃耗初期PACS聚合物可燃毒物有较低的初始k_(inf)值,而在燃耗后期释放高于1%的k_(inf)值,可燃吸收体核素B-10消耗更加充分,且具有较大的热通量,可提高热中子利用率,并促进裂变核素Pu的消耗。     

Gd burnable poison system for reactivity control of the first cycle of a PWR

The reactivity control of a PWR core may be performed by a system of burnable poison (BP) rods. In such a case, the soluble B system may be eliminated and the BP rods will be responsible for the excess reactivity provided for fuel depletion and fission products accumulation. A strong negative moderator temperature coefficient is a desirable safety feature, inherent to a poison-free moderator. The design objective of a PWR core controlled completely by a system of BP rods is achieved by utilization of Gd as the poison material and annular geometry of a BP rod. The proposed concept is tested as a retrofittable option for the current generation, as well as new PWR plants. A plausible incore fuel-management scheme is demonstrated, with planar power distribution, close to an acceptable range. The fuel-cycle penalty due to the residual poison content at EOC is relatively small.     

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。      

Recommended strategy and limitations of burnable absorbers used in VVER fuel assemblies

There is an obvious effort to increase the burn up of used fuel assemblies in order to improve fuel utilization.A more effective operation can be realized by extending the fuel cycles or by increasing the number of reloadings.This change is nevertheless connected with increasing the uranium enrichment even above 5% of 235 U. Burnable absorbers are widely used to compensate for the positive reactivity of fresh fuel. With proper optimization, burnable absorbers decrease the reactivity excess at the beginning of the cycle, and they can help with stabilization of power distribution. This paper describes properties of several materials that can be used as burnable absorbers. The change in concentration or position of the pin with a burnable absorber in a fuel assembly was analyzed by the HELIOS transport lattice code. The multiplication factor and power peaking factor dependence on fuel burn up were used to evaluate the neutronic properties of burnable absorbers. The following four different materials are discussed in this paper: Gd_2O_3, IFBA, Er_2O_3,and Dy_2O_3.Gadolinium had the greatest influence on fuel characteristics. The number of pins with a burnable absorber was limited in the VVER-440 fuel assembly to six. In the VVER-1000 fuel assembly, 36 pins with a burnable absorber can be used as the assembly is larger. The erbium depletion rate was comparable with uranium burn up.Dysprosium had the largest parasitic absorption after depletion.     

FCM燃料压水堆弥散可燃毒物中子学分析

为将全陶瓷微胶囊封装（FCM）燃料应用于小型压水堆,对FCM燃料组件开展了可燃毒物中子学设计与分析。通过寿期初引入负反应性、寿期内消耗速率和寿期末残留3个方面,对弥散在SiC基体中的弥散型可燃毒物Gd₂O₃、Er₂O₃、Sm₂O₃、Eu₂O₃、Dy₂O₃及HfO₂进行评价。FCM燃料中TRISO颗粒核芯直径达800 μm,燃料颗粒自屏效应强烈,在RMC程序中引入随机介质计算功能,对FCM燃料进行随机几何建模,保证了反应性计算精度。分析表明：Er₂O₃可作为FCM燃料堆芯的候选可燃毒物,Gd₂O₃和Eu₂O₃需结合堆芯开展进一步研究,Sm₂O₃、Dy₂O₃及HfO₂的反应性惩罚过大,不适合作为FCM燃料可燃毒物。     

Optimization of PWR fuel assembly radial enrichment and burnable poison location based on adaptive simulated annealing

The focus of this paper is to present a concurrent optimization scheme for the radial pin enrichment and burnable poison location in PWR fuel assemblies. The methodology is based on the Adaptive Simulated Annealing (ASA) technique, coupled with a neutron lattice physics code to update the cost function values. In this work, the variations in the pin U-235 enrichment are variables to be optimized radially, i.e., pin by pin. We consider the optimization of two categories of fuel assemblies, with and without Gadolinium burnable poison pins. When burnable poisons are present, both the radial distribution of enrichment and the poison locations are variables in the optimization process. Results for 15 × 15 PWR fuel assembly designs are provided.     

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.