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J

Junli Gou

西安交通大学

H指数:13

被引数:648

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Optimization and characteristic analysis of the heat pipe reactor core with U-50Zr metallic fuel under load-variation conditions

在负载变化条件下以U-50Zr金属燃料为燃料的热管反应堆堆芯的优化与特性分析

IF9.4

2026-07-310

PRE

A Softmax-based neural network surrogate model with uncertainty estimation for nuclear system prediction

基于Softmax的神经网络代理模型及其不确定性估计用于核系统预测

Progress in Nuclear Energy

IF3.2

2026-05-270

PRE

Optimization of the load-following strategy and fault operation analysis for a compact megawatt nuclear power system

紧凑型兆瓦级核动力系统的负荷跟踪策略优化与故障运行分析

IF9.4

2025-11-250

PRE

A data-driven multi-physics coupling analysis method for multi-objective optimization design of an innovative heat pipe reactor core

一种基于数据驱动的多物理场耦合分析方法，用于创新型热管反应堆芯的多目标优化设计

COMPUTER PHYSICS COMMUNICATIONS

IF3.4

2025-06-010

PRE

Preliminary design and experimental study of heat transfer characteristics of a passive residual heat removal system for a heat pipe cooled reactor

APPLIED THERMAL ENGINEERING

IF6.9

2025-06-010

PRE

Research on start-up strategy optimization for a compact megawatt nuclear power system based on surrogate model construction and genetic algorithm

APPLIED THERMAL ENGINEERING

IF6.9

2025-02-010

PRE

Preliminary analysis of startup transient for an ultra-small lithium-cooled space reactor power system

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-03-013

OAAI

Study on start-up characteristics of a heat pipe cooled reactor coupled with a supercritical CO2 Brayton cycle

耦合超临界CO2布雷顿循环的热管冷却堆启动特性研究

APPLIED THERMAL ENGINEERING

IF6.9

2024-01-0119

PRE

Neutronic-thermalhydraulic coupling analysis of heat pipe failure accidents of a new type of megawatt heat pipe reactor

APPLIED THERMAL ENGINEERING

IF6.9

2024-01-017

PRE

A novel approach on designing ultrahigh burnup metallic TWR fuels: Upsetting the current technological limits

IF4.9

2022-11-031

OAAI

Development and validation of a two-fluid three-field model for the vertical upward flow

PROGRESS IN NUCLEAR ENERGY

IF3.2

2021-11-017

PREAI

Investigation on risk-informed uncertainty method and its application in PWR LBLOCA

PROGRESS IN NUCLEAR ENERGY

IF3.2

2021-09-010

PREAI

Optimization of sensitivity analysis in best estimate plus uncertainty and the application to large break LOCA of a three-loop pressurized water reactor

PROGRESS IN NUCLEAR ENERGY

IF3.2

2020-08-017

PREAI

Analysis of SBLOCA on CPR1000 with a passive system

NUCLEAR SCIENCE AND TECHNIQUES

IF3.8

2016-12-016

PREAI

Preliminary safety analysis on loss of flow accidents and external source transients for LBE cooled ADSR core

PROGRESS IN NUCLEAR ENERGY

IF3.2

2016-04-017

PREAI

Thermal-hydraulic design and transient analysis of passive cooling system for CPR1000 spent fuel storage pool

CPR1000乏燃料储存池非能动冷却系统热工水力设计及瞬态分析

NUCLEAR SCIENCE AND TECHNIQUES

IF3.8

2016-02-273

PREAI