Neutronics相关论文
The neutronic properties of molten salt reactors (MSRs) differ from those of traditional solid fuel reactors owing to th......
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It can be difficult to calculate some under-sampled regions in global Monte Carlo radiation transport calculations. The ......
Core and blanket thermal–hydraulic analysis of a molten salt fast reactor based on coupling of OpenM
In the core of a molten salt fast reactor (MSFR), heavy metal fuel and fission products can be dissolved in a molten flu......
Molten salt-cooled reactor is one of the six Gen-Ⅳ reactors with promising characteristics including safety,reliability......
In this study, COMSOL v5.2 Multiphysics software was utilized to perform coupled neutronics and thermal-hydraulics simul......
Neutronics studies for a solid target have been done with Monte Carlo high-energy particle transport code NMTC/JAM,when ......
Neutronics Optimization of LiPb-He Dual-Cooled Fuel Breeding Blanket for the Fusion-Driven sub-criti
本文通过对荣华二采区10...
NECP-SARAX是西安交通大学NECP团队开发的用于快中子反应堆的中子学程序系统。为准确处理快中子反应堆中中等质量核素散射共振以及......
Neutronics Optimization of LiPb-He Dual-Cooled Fuel Breeding Blanket for the Fusion-Driven sub-criti
The concept of the liquid Li17Pb83 and Helium gas dual-cooled Fuel Breeding Blanket (FBB) for the Fusion-Driven sub-crit......
Steady state investigation on neutronics of a molten salt reactor considering the flow effect of fue
The Molten Salt Reactor (MSR),one of the‘Generation Ⅳ'concepts,is a liquid-fuel reactor,which is different from the co......
The neutronic properties of molten salt reactors(MSRs)differ from those of traditional solid fuel reactors owing to thei......
One of the most important safety parameters taken into consideration during the design and actual operation of a nuclear......
采用类似于大亚湾900 MW压水堆的堆芯模型，使用燃料组件计算程序 CASMO4E和反应堆稳态分析程序SIMULATE3分别对铀燃料组件、铀钚燃......
基于聚变实验装置（ＪＥＴ）及其物理实验已达到的Ｄ－Ｔ等离子体参数水平，在一维燃耗计算和分析的基础上，给出了氚自持、年可处理１１个左右标准压水堆（３００ＭＷ）年......
用MCNP软件计算反应堆冷中子源，慢化剂室内平均中子注量率为6．69×10^13／cm^-2·s^-1，波长为0．411113和0．6nm的冷中子增益因子-1......
使用IAEA基准池式纳冷快堆例题BN 600对FDS团队自主开发的大型集成多功能中子学计算分析系统VisualBUS4进行测试,通过与国际上其他......
选取加速器驱动的快堆作为核燃料增殖堆。在堆芯，燃料形式为（Ｕ－Ｐｕ）Ｏｘ，在转换区，ＴｈＯ２被选为增殖材料以生产＾２３３Ｕ。由于Ｐｂ的中子学性能和化学性能优于Ｎａ，因而被......
对聚变驱动次临界堆的多功能双冷核废料嬗变包层进行了中子学设计和分析,设计目标是:①氚和钚燃料自持;②较少的初装料得到较高的......
基于ITER装置全模型，借助于MCNP自动建模程序MCAM，将TBM模块插入该模型的赤道窗口，使用MCNP／4C和FENDL1．0数据库，对DLL和SLL两个典型子模......
采用VisualBUS程序和HENDL数据库，对聚变驱动乏燃料焚烧堆氦冷包层开展了中子学设计与分析工作，设计目标是在满足Keff小于0．95，功率密......
采用球形托卡马克（sT）等离子体位形，对氦冷嬗变包层、钠冷嬗变包层、氟锂铍（FLiBe）熔盐冷嬗变包层三种嬗变包层中子学方案进行了初步计......
基于先进核数据库ENDF/B-VI和计算机程序对ST嬗变堆中心柱的中子学及辐照损伤的二维分析计算结果,分别对中心柱导体因中子辐照影响......
采用三维中子学程序MCNP及FENDL2．0数据库，对具有3×3子模块结构的中国氦冷固体增殖剂（HCSB）的氚增殖包层模块（TBM）进行了三维中子学......
本文主要对聚变-裂变混合堆增殖乏燃料在压水堆组件中使用的可能性进行了初步研究。根据聚变-裂变混合堆增殖乏燃料的特点,给出了......
氦气、水、熔盐(Flibe)在强磁场中流动不存在严重的MHD问题,因此适合在基于磁约束的聚变-裂变混合堆中作为冷却剂。针对氦气、水、......
聚变裂变混合堆比纯聚变堆在工程及技术方面要求低,且在产生核燃料、嬗变长寿命核废料以及固有安全性方面具有一定优势,因此,越来......
聚变裂变混合堆在增殖核燃料、嬗变长寿命核废料及固有安全性等方面具有较大优势,同时,它比纯聚变堆在工程及技术方面要求低,因此......
为了满足ITER对波纹度的要求,核工业西南物理研究院提出了新的减少低活化铁素体钢的氦冷固态（HCSB）实验包层模块（TBM）设计方案。采用MC......
为满足中国聚变工程实验堆（CFETR）包层的应用要求,本文提出氦冷陶瓷增殖（HCCB）包层方案。为验证HCCB包层设计方案的合理性与可行性,采......
采用压水堆17×17燃料组件模型,用燃料组件参数计算程序DRAGON分别对混合堆增殖钍燃料组件和全铀组件的中子学特性进行了研究,......
Study of Criticality Safety and Neutronic Performance for a 348-Fuel-Pin Ghana Research Reactor-1 LE
The National Nuclear Research Institute of the Ghana Atomic Energy Commission is undertaking steps to convert the Ghana ......
Study of Criticality Safety and Neutronic Performance for a 348-Fuel-Pin Ghana Research Reactor-1 LE
The National Nuclear Research Institute of the Ghana Atomic Energy Commission is undertaking steps to convert the Ghana ......
Molten salt-cooled reactor is one of the six GenIV reactors with promising characteristics including safety,reliability,......
In this study,COMSOL v5.2 Multiphysics software was utilized to perform coupled neutronics and thermal–hydraulics simul......
本文对聚变-裂变混合实验堆固体增殖剂包层的中子学行为进行了一维、二维和三维计算分析和比较。为了便于模拟复杂的托卡马克环形......
Core and blanket thermal-hydraulic analysis of a molten salt fast reactor based on coupling of OpenM
In the core of a molten salt fast reactor(MSFR),heavy metal fuel and fission products can be dissolved in a molten fluor......
Innovative nuclear reactor concepts such as the Accelerator Driven Systems (ADSs) have imposed extra requirements of sim......
Analysis of Neutronics and Thermal-Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PW
This paper presents a comparative analysis of different parameters such as enthalpy, moderator temperature, moderator de......
The Nigeria Research Reactor-1 (NIRR-1) is one of the Commercial Miniature Neutron Source Reactors (MNSRs) sited outside......
