高通量工程试验堆物理计算方法的研究

研究了高通量工程试验堆堆芯栅元计算模型 ,特别是多层套管燃料组件的计算模型 ;提出了控制棒扩散系数修正方法 ;开发了栅元计算程序WIMS D4 CNPRI和六角形堆芯扩散计算程序CITATION/SIXTUS 2 / 3软件包 ,并成功的将它们用于高通量工程试验堆的物理计算。     

遗传算法用于MJTR堆芯装载方案优化

应用遗传算法 ,编制了MJTR堆芯装载方案优化计算程序 ;设计了与问题特性有关的编码与交叉算子 ,用两维六角形栅元节块扩散程序SIXTUS 2作适值计算。为提高程序的质量与效率 ,通过试算找出多个计算方法与参数的优化选择。MJTR各炉装载方案的优化计算结果表明 ,遗传算法的优化方案全都好于已被采用的专家方案。给出了MJTR堆芯装载方案的优化模式与优化方案     

遗传算法在HFETR堆芯优化设计中的应用

研究遗传算法在HFETR堆芯优化设计中的应用。计算程序中部分参数采用岷江试验堆堆芯优化程序中已采用的参数，计算方法上引入了对称变异算子与虚拟堆芯技术。虚拟堆芯技术的引入减少了获得优化方案的计算时间，而对称变异算子的应用增加了优化方案的工程实用性。从优化结果可以看出，转换比与同位素总产量都可提高10％以上，优化堆芯装载方案对称实用。满足工程要求。     

研究试验堆堆芯最佳倒料原理及其应用

本文根据堆芯倒料的基本关系式,提出了不同燃耗深度燃料元件堆芯的最佳倒料原理和由这一原理得出的几点结论。给出了不同倒料方式的计算公式,编制了计算程序并对高通量工程试验堆(HFETR)典型堆芯装载的不同倒料方式作了计算。应用文中提出的堆芯燃料元件耗用指标,分析了HFETR十年来24炉运行的堆芯燃料管理工作。结果表明,应用最佳倒料原理可大量节省燃料元件。本文还讨论了HFETR堆芯燃料管理研究的方向。     

压水堆核电厂换料堆芯装载优化专家系统SERION／INCORE研制

依赖于专家知识建立了大亚湾核电站和秦山第二核电厂换料堆芯装载知识库，在此基础上进行换料堆芯装载方案启发式优化搜索。应用已用工程设计的二维细网堆芯燃料管理程序系统（INCORE）进行装转方案评介，采用循环长度和堆芯功率峰因子综合指标计算装载方案的价值并评价其优劣程度，用该系统分别对大亚湾核电站二号堆第四循环和秦山第二核电厂第四循环芯优化方案搜索计算。结果表明，无论从堆芯径向功率峰因子还是从循环长度指标来看，专家系统SEDRION／INCORE搜索得到的装载方案都明显优于参考方案。     

M310改进型核电机组年换料堆芯装料操作方案研究

M310改进型核电机组年换料堆芯在装料操作过程中存在困难，通过M310改进型核电机组年换料堆芯的布置、燃料组件变形形式和装载措施的研究，福清核电厂1号机组第2次大修堆芯装料操作方案为例，基于对燃料组件变形特性的分析和装载基本假设，对现有的“蛇形”装料法进行深入分析，提出修正最后3排燃料组件的装载次序的优化改进方案。经实际装料验证，优化后的年换料堆芯装料操作方案是可行的，能显著提高装料的安全性与效率。      

压水堆核电厂换料堆芯装载优化专家系统SEDRIO/INCORE研制

依赖于专家知识建立了大亚湾核电站和秦山第二核电厂换料堆芯装载知识库,在此基础上进行换料堆芯装载方案启发式优化搜索。应用已用于工程设计的二维细网堆芯燃料管理程序系统(INCORE)进行装载方案评价,采用循环长度和堆芯功率峰因子综合指标计算装载方案的价值并评价其优劣程度。用该系统分别对大亚湾核电站二号堆第四循环和秦山第二核电厂第四循环堆芯优化方案搜索计算。结果表明,无论从堆芯径向功率峰因子还是从循环长度指标来看,专家系统SEDRIO/INCORE搜索得到的装载方案都明显优于参考方案。     

大功率压水堆堆芯燃料管理设计

设计了一种大功率压水堆堆芯,对其中可燃毒物装载方案、平衡循环布置、首循环装料及过渡循环方案进行了研究。采用特征统计算法CSA燃料管理优化程序,快速高效地搜索堆芯装载和可燃毒物配置优化方案。采用堆芯核设计程序CPACT进行全堆计算,结果真实可靠。分别设计了18个月和24个月换料两种方案,计算结果表明,在满足堆芯燃料管理所有限值要求的前提下,两种方案均从第4循环开始进入平衡循环。     

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。     

330 MW环形燃料小型堆方案设计

本文研究了应用环形燃料的小型压水堆堆芯燃料富集度、换料批次、循环长度以及平均卸料燃耗之间的匹配规律。根据设计准则和目标设计了热功率为330 MW的环形燃料小型堆堆芯装载和燃料管理方案,并采用CMS程序包对过渡循环到平衡循环的堆芯关键性能参数进行计算分析,功率不均匀因子、反应性系数、停堆裕量等均符合设计准则要求,堆芯稳态物理特性良好。     

岭澳核电站1/4换料燃料管理方案研究

对岭澳核电站1/4(堆芯)换料项目中的燃料管理方案研究工作进行了描述,从1/4换料燃料管理目标的提出,到最终方案的确定,详细解释了所采用的软件、方法及所进行的研究.文中并给出了在电站应用后的试验验证结果.最后,从燃料管理的角度,就采用1/4换料后对电站带来的有利及不利之处进行了分析.     

百万千瓦级环形MOX燃料堆芯设计

对环形UO2燃料及环形MOX燃料组件参数的计算方法进行了研究。设计了包含193盒环形UO2和MOX燃料组件的混合型长周期(18个月)堆芯方案。对设计的堆芯的重要物理参数进行了分析,并对各循环进行了燃耗计算。结果表明,装载约30%MOX组件的堆芯可在百万千瓦功率下实现长周期换料。堆芯从初装载可安全过渡到平衡循环,各循环的重要物理参数均满足设计要求,说明设计的堆芯及燃料管理方案是安全可行的。     

COPERNICUS: A multi-cycle optimization code for nuclear fuel based on parallel simulated annealing with mixing of states

COPERNICUS is the Studsvik code for performing nuclear fuel optimization over a multi-cycle planning horizon that provides for an implicit coupling between traditionally separate in-core and out-of-core fuel management decisions. These decisions include determination of: fresh fuel region size; sub-region enrichments and bundle designs; exposed fuel re-use; and core loading pattern. The COPERNICUS methodology is based on a parallel implementation of the Simulated Annealing optimization algorithm, modified by the technique of Mixing of States, that allows for deployment in a processor scalable environment. COPERNICUS utilizes the 3-D licensing grade code SIMULATE for evaluation of all core loading pattern constraints, such as those involving reactivity and thermal margin requirements. Results are presented for a transition cycle design that compares performance of multi-cycle optimization to successive, single cycle optimization with regard to reducing levelized fuel costs.     

启明星Ⅱ号零功率装置铅堆堆芯首次物理启动

启明星Ⅱ号铅堆堆芯的首次物理启动旨在完成国内首座铅冷快堆零功率装置的装料与达临界,掌握堆芯安全特性。考虑铅堆堆芯使用两种燃料元件,临界元件数量较大,不同区域的中子能谱与燃料元件价值差异大的特点,首次物理启动对启动中子源与中子计数探测器进行了选取与验证,评价了模拟元件对中子的散射与吸收的影响,制定了分区外推的装料方案。按照装料方案,铅堆堆芯完成了装料,安全实现了首次临界,测量了模拟元件、燃料元件、安全棒和调节棒反应性。本文工作为后续实验运行提供了重要的实验参数与临界装载方案。     

Optimization of Refueling Scheme of Fast Reactor Core by Means of Man Machine Interactive Method

A computer system for performing quick survey and optimization has been developed to aid in-core fuel management of sodium cooled fast reactors. The method utilizes the conversational mode of computer operation, to perform on-line computation, display of results and acceptance of commands, thus permitting rapid exchange of information between the machine and the person in charge. To improve the overall efficiency of the system as problem-solver, an algorithm is introduced to provide for automated shuffling to determine the fuel loading patterns of successive cycles. This algorithm serves to model the refueling and shuffling arrangement after a prescribed optimized standard core pattern according to the extent of burnup of each fuel sub-assembly.

The proposed system is applied to problems of: (1) straightforward simulation of fuel performance in given in-core fuel management programs, covering core and radial blanket refueling and control rod positioning, (2) optimization, and (3) modification of in-core fuel management programs.

Several numerical examples are treated, to confirm the applicability of this conversational-mode problem-solving system to in-core fuel management.     

157组燃料组件组成的堆芯燃料管理研究

本文应用SCIENCE程序包对157组燃料组件组成的压水堆堆芯进行换料优化燃料管理研究,给出了3个年换料和2个18个月换料共5个设计方案,每个设计方案给出了从首循环到第8循环共8个循环的主要计算结果,并进行了分析比较。综合来看,OUT-IN装载的设计方案功率峰值偏低,IN-OUT装载的设计方案功率峰值偏高,但均在设计限值以内;1/4堆芯换料设计方案的平均卸料燃耗最深,表明其组件燃耗得最充分,经济性较好。     

Application of the Robust Design Concept for Fuel Loading Pattern

Application of the robust design concept for fuel loading pattern design is proposed as a new approach to improve the prediction accuracy of core characteristics. The robust design is a design concept that establishes a resistant (robust) system for perturbations or noises, by properly setting design variables. In order to apply the concept of robust design to fuel loading pattern design, we focus on a theoretical approach based on the higher order perturbation method. This approach indicates that the eigenvalue separation is one of the effective indices to measure the robustness of a designed fuel loading pattern. In order to verify the effectiveness of the eigenvalue separation as an index of robustness, numerical analysis is carried out for typical 3-loop PWR cores, and we evaluated the correlation between the eigenvalue separation and the variation of relative assembly power due to the perturbation of the cross section. The numerical results show that the variation of relative power decreases as the eigenvalue separation increases; thus, it is confirmed that the eigenvalue separation is an effective index of robustness. Based on the eigenvalue separation of a fuel loading pattern, we discuss design guidelines of a fuel loading pattern to improve the robustness. For example, if each fuel assembly has independent uncertainty on its cross section, the robustness of the core can be enhanced by increasing the relative power at the center of the core. The proposed guidelines will be useful to design a loading pattern that has robustness for uncertainties due to cross section, calculation method, and so on.     

PWR fuel management optimization using continuous particle swarm intelligence

The objective of nuclear fuel management is to minimize the cost of electrical energy generation subject to operational and safety constraints. In the present work, a core reload optimization package using continuous version of particle swarm optimization, CRCPSO, which is a combinatorial and discrete one has been developed and mapped on nuclear fuel loading pattern problems. This code is applicable to all types of PWR cores to optimize loading patterns. To evaluate the system, flattening of power inside a WWER-1000 core is considered as an objective function although other variables such as K_eff along power peaking factor, burn up and cycle length can be included. Optimization solutions, which improve the safety aspects of a nuclear reactor, may not lead to economical designs. The system performed well in comparison to the developed loading pattern optimizer using Hopfield along SA and GA.     

关于PWR及CANDU堆先进燃料管理策略的研究

阐述开展先进燃料管理策略研究的必要性与紧迫性。对我国秦山核电厂的燃料管理策略的改进进行了初步探讨,包括提高富集度延长循环长度、增大平均卸料燃耗、应用先进可靠毒物和低泄漏优化换料、改进燃料组件设计和适当提高功率等,并对可能取得的重大经济效益进行了讨论。提出研究ＰＷＲ的乏燃料在ＣＮＡＤＵ堆中应用及形成ＰＷＲ／ＣＡＮＤＵ联合燃料循环的可行性,以提高燃耗深度,增加能量输出,降低发电成本。