位置：成果数据库 > 期刊 > 期刊详情页
Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport method
  • ISSN号：2954-93
  • 期刊名称：Nuclear Engineering and Design
  • 时间：2015
  • 页码：489-499
  • 相关项目：加速器驱动次临界堆嬗变次锕系与长寿命裂片核素的安全性影响与机理研究
作者： Youqi Zheng|Kunpeng Wang|Xunzhao Li|Shengcheng Zhou|
同期刊论文项目
加速器驱动次临界堆嬗变次锕系与长寿命裂片核素的安全性影响与机理研究
期刊论文 53 会议论文 80
同项目期刊论文
Code development for eigenvalue total sensitivity analysis and total uncertainty analysis
基于预估修正改进准静态方法的中子时空动力学研究
Economics analysis of fuel cycle cost of fusion–fission hybrid reactors based on different fuel cycl
基于单通道模型的ADS堆芯物理热工耦合计算
瞬发中子密度衰减法计算中子代时间
Studies on LLFP transmutation in a pressurized water reactor
Preliminary design studies of an industrial scale accelerator-driven minor actinide burner
Coupled Analysis and improvements for Canadian-SCWR core design
LAVENDER: A steady-state core analysis code for design studies of accelerator driven subcritical rea
Improvements of the subgroup resonance calculation code SUGAR
A deterministic and Monte Carlo coupling method for PWR cavity radiation streaming calculation
压水堆高放长寿命裂变产物堆内嬗变平衡循环设计
AN IMPROVED RESONANCE SELF-SHIELDING CALCULATION METHOD BASED ON EQUIVALENCE THEORY
Three-Dimensional Invere Transport Solver Based on Compressive Sensing Technique
Burnup calculations of light water-cooled pressure tube blanket for a fusion-fission hybrid reactor
Pre-conceptual core design of SCWR with annular fuel rods
A code development for LLFP transmutation analysis based on the whole Pin-Wise calculation in PWRs
NAPTH:Neutronics analysis code system for the fusion-fission hybrid reactor with pressure tube tybe
加速器驱动次临界堆芯中子学程序开发
NECP软件包中NECL子群数据与任意几何共振模块研制
A fusion-fission hybrid reactor with water-cooled pressure tube blanket for energy production
NAPTH: Neutronics analysis code system for the fusion fission hybrid reactor with pressure tube type
Study on three-dimensional heterogeneous calculation of ITER test blanket module with deterministic
Thorium-Uranium Fuel Cycle based on Fusion-Driven Subcritical Reactor and PWR
Streaming Gauss-Seidel nodal sweeping scheme for PWR pin-by-pin calculation
Improvement and Validation of a Nodal-SP3 Code for Whole Core Pin-by-pin Calculation
Calculation of effective delayed neutron fraction with modified library of Monte Carlo code
加速器驱动的次临界系统初步概念设计
ITER实验包层模块的三维确定论方法计算
改进双排棒组件超临界水堆堆芯设计
ADS启明星1#次临界反应堆缓发中子有效份额的测量
在MCNP中考虑共振弹性散射的修正方法
径向倒料式驻波堆堆芯概念设计
中国加速器驱动次临界系统常规磁铁的磁场测量
聚变裂变混合堆燃耗计算及燃料成本分析
铅铋冷却氮化物燃料小型模块化反应堆堆芯中子学特性分析
加速器驱动次临界嬗变堆的参数敏感性分析
工业加速器驱动次临界嬗变堆的设计分析
Am装载对加速器驱动次临界系统瞬态过程的影响分析