critical reactor是什么意思

网络释义

用法例句

Optimization of first wall structure and shape of helium flow channel of the dual-cooled waste transmutation blanket for the fusion driven sub-critical system;

聚变次临界堆双冷嬗变包层第一壁结构和氦气流道优化分析

Optimization of design parameters based on minimizing the cost of electricity of the fusion-driver sub-critical system;

基于最小化发电成本的聚变驱动次临界堆参数优化分析

Thermal stress calculation and analysis on first wall structure of dual-cooled waste transmutation blanket for the fusion drive n sub-critical system;

聚变驱动次临界堆双冷嬗变包层第一壁结构热应力计算与分析

Economic analysis of the fusion-driven subcritical system;

聚变驱动次临界堆经济性分析

Neutronic optimal analysis for the transmutation of long-lived fission products in the blanket for the fusion-driven subcritical system;

长寿命裂变产物在聚变驱动次临界堆包层中嬗变的中子学优化分析

Neutronic optimization based on genetic algorithm for the initial loading long-lived minor actinides in the blanket for the fusion-driven subcritical system;

基于遗传算法的聚变驱动次临界堆嬗变包层长寿命锕系元素初装料中子学优化

Neutronic design and analysis of dual-cooled waste transmutation blanket for the fusion driven sub-critical system;

聚变驱动次临界堆双冷嬗变包层中子学设计与分析

Core plasma parameters design and analysis for the fusion driven sub-critical system;

聚变驱动次临界堆聚变堆芯参数设计与分析

Conceptual design study on the fusion-driven sub-critical system;

聚变驱动次临界堆概念设计研究

Core plasma parameters design and analysis for the fusion driven sub-critical system

聚变驱动次临界堆聚变堆芯参数设计与分析

CONCEPTUAL RESEARCH ON REACTOR CORE PHYSICS FOR ACCELERATOR DRIVEN SUB CRITICAL REACTOR

加速器驱动次临界堆堆芯物理概念研究

Activation characteristics of the dual-cooled w aste transmutation blanket for the fusion-driven subcritical system

聚变驱动次临界堆双冷嬗变包层材料活化计算与分析

engineering test reactor critical assembly

工程试验堆临界装置

Coupled Thermal-Hydraulics and Neutron-Physics Analysis of Supercritical Water Cooled Reactor With Mixed Spectrum Core

混合能谱超临界水堆堆芯热工-物理性能分析

Preliminary Design of Sub-critical Reactor Core for Accelerator Driven System with Three Proton Beams

三束流驱动ADS次临界反应堆堆芯初步设计

Critical Avalanche Exponents of One-dimensional Self-organized Critical Rice-pile Model

一维自组织临界米堆模型的临界雪崩指数

maritime gas-cooled reactor critical experiment

气冷式海上反应堆临界试验装置

advanced test reactor critical experiment

先进试验堆临界实验装置

Corrosion Behaviors of Candidate Materials for Supercritical-Cooled Water Reactor

超临界水堆候选材料的腐蚀特性研究

Neutronics/thermal-hydraulics coupled axial 1D model for SCWR core static analysis

超临界水堆堆芯轴向一维物理热工耦合稳态分析

Nuclear criticality safety for fissile materials outside reactors--Administrative regulation for nuclear criticality safety

GB15146.1-1994反应堆外易裂变材料的核临界安全核临界安全行政管理规定

Analysis of Candidate Core Materials in SCWR Based on Boiler Materials of SCU

基于超临界火电站锅炉用材的超临界水冷却反应堆堆芯候选材料分析

Study on the Sandpiles Complex Phenomena and Self-Organized Critical System;

沙堆模型复杂性现象及自组织临界性系统研究

Research on the Dynamic Characteristic of Sand-Pile Evolvement and the Self-Organized Critical Phenomena;

沙堆演化动态特性及自组织临界现象研究

Experiment Study on Build-up Welding Shaft Journal of Intermediate Pressure Rotor in Ultra-Supercritical Steam Turbine;

超超临界汽轮机中压转子轴径堆焊试验研究

Research on Designing the Outlet Nozzle in Main Vessel of Supercritical Water Reactor;

超临界水冷堆主容器出口管的设计研究

Studies and Design of the Fast Zone Assembly in SCWR Mixed Core

超临界水冷混合堆快谱组件研究与设计