郑友奇

2026

[Review] Digital competence for sustainable education of pre-service teachers: a systematic literature review (2014-2024)

Frontiers In Psychology，Vol. 16

DOI

2025

非英语专业大学生二语自我、外语愉悦与英语学业成就关系研究

《宿州职业技术学院学报》

DOI

2025

Advancements and challenges in small modular lead/lead bismuth eutectic cooled fast reactors: A 30-year overview

Annals of Nuclear Energy

DOI

2025

Neutronics calculation and analysis of a small lead-bismuth fast reactor core with control rods integrated within fuel assemblies

Annals of Nuclear Energy

DOI

2025

Feasibility study on the core design of high-flux fast neutron research reactors

Nuclear Engineering and Technology

DOI

2025

Uncertainty quantification and nuclear data adjustment of physical calculation parameters of lead-bismuth fast reactor core

Nuclear Techniques

DOI

2025

Research Advances on High-Fidelity Neutronics Computational Methods and Applications for Advanced Nuclear Reactors

Chinese Science Bulletin

DOI

2025

Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems

Annals of Nuclear Energy

DOI

2024

高校外语课程思政教学实施路径思考

《江苏外语教学研究》

2024

Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method

Nuclear Engineering and Technology

DOI

2023

基于学生视角新文科背景下翻译专业人才培养路径优化研究

《牡丹江教育学院学报》

2023

The Low-Enriched Uranium Core Design of a Mw Heat Pipe Cooled Reactor

Social Science Research Network

DOI

2023

Dynamic analysis on reactivity oscillation by the movement of the piston in integrated space nuclear reactor

Annals of Nuclear Energy

DOI

2023

Development of optimal framework SARAX/DAKOTA for multiple objective optimization of fast reactor and its application

Nuclear Engineering and Design

DOI

2023

The applicability study and validation of TULIP code for full energy range spectrum

Nuclear Engineering and Technology

DOI

2023

The Acceleration of Improved Tone's Method in Advanced Reactor Lattice Neutron Spectrum Calculation

Social Science Research Network

DOI

2023

Uncertainty analysis of the China experimental fast reactor start-up tests based on refined calculation results

Annals of Nuclear Energy

DOI

2023

Multi-parameter nuclear data adjustment for sodium fast reactor

Progress in nuclear energy (New series)

DOI

2023

Development and verification of the coupling code of discrete ordinates and Monte Carlo methods

Annals of Nuclear Energy

DOI

2022

趋近化理论视角下的国家形象构建研究——以习近平主席在2022年世界经济论坛上的视频演讲为例

《浙江外国语学院学报》

2022

Investigation on a new scheme for the transient simulation of the research pulsed reactor

Annals of Nuclear Energy

DOI

2022

Preliminary conceptual design and analysis of a 100 kWe level Nuclear Silent Thermal‐Electrical Reactor (NUSTER‐100)

International Journal of Energy Research

DOI

2022

Validation of TULIP via ICSBEP Critical Benchmark

Volume 15: Student Paper Competition

DOI

2022

A Stable Condition and Adaptive Diffusion Coefficients for the Coarse-Mesh Finite Difference Method

Frontiers in Energy Research

DOI

2022

Development of SARAX code system for full-range spectrum adaptability in advanced reactor analysis

DOI

2022

An IFDF accelerated parallel nodal SN method for XYZ geometry in SARAX code system

Annals of Nuclear Energy

DOI

2021

The discrete ordinate method

DOI

2021

Improved block-Jacobi parallel algorithm for the S nodal method with unstructured mesh

DOI

2021

Verification of SARAX code system in the reactor core transient calculation based on the simplified EBR-II benchmark

Nuclear Engineering and Technology

DOI

2021

Reactor design of UPR-1: A MW-level reactor for unmanned underwater vehicle propulsion using low-enriched uranium

DOI

2021

A method for calculating the assembly bowing reactivity coefficients in sodium fast reactor

Annals of Nuclear Energy

DOI

2021

Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation

Energies

DOI

2021

Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER

DOI

2021

Other methods

Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation

DOI

2020

儿童文学汉译本的翻译美学解读——以《芒果街上的小屋》潘帕译本为例

《江苏外语教学研究》

2020

NECP-hydra: A high-performance parallel S code for core-analysis and shielding calculation

DOI

2020

Nuclear-data adjustment based on the continue-energy cross-section library for the fast reactor

DOI

2020

On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX

DOI

2020

A parallel DSA algorithm in the 3-D cylindrical geometry

Annals of Nuclear Energy

DOI

2020

Extension of SARAX code system for reactors with intermediate spectrum

DOI

2020

A new hexagonal-Z nodal SN method in SARAX code system

DOI

2020

Study of the PWR ex-core detector response simulation based on the 3D S method

DOI

2020

Validation of SARAX code system using the SFR operational tests

DOI

2020

IFDF acceleration method with adaptive diffusion coefficients for SN nodal calculation in SARAX code system

DOI

2019

论科普翻译中的文学性再现

《江苏外语教学研究》

2019

英语专业大学生成就目标定向与元认知能力的关系研究

《教学研究》

2019

Uncertainty quantification of sodium-cooled fast reactor based on the UAM-SFR benchmarks: From pin-cell to full core

Annals of Nuclear Energy

DOI

2019

Validation of SARAX for the China Fast Reactor with the extrapolated experimental data

Annals of Nuclear Energy

DOI

2019

Corrigendum to ‘Uncertainty quantification of sodium-cooled fast reactor based on the UAM-SFR benchmarks: From pin-cell to full core’ [Ann. Nuclear Energy 128 (2019), 433–442]

Annals of Nuclear Energy

DOI

2019

Sensitivity analysis and similarity evaluation of sodium-cooled fast reactor in large size

Annals of Nuclear Energy

DOI

2019

Improvement of few-group cross-section generation in fast reactor analysis system SARAX

Annals of Nuclear Energy

DOI

2018

人文社科类学术期刊微信公众号中论文标题语用策略的顺应性分析

《浙江外国语学院学报》

2018

Flexibility of ADS for minor actinides transmutation in different two-stage PWR-ADS fuel cycle scenarios

DOI

2018

Development of an Optimized Transport Solver in SARAX for Fast Reactor Analysis

Volume 9: Student Paper Competition

DOI

2018

Improved Variational Nodal Method Based on Symmetry Group Theory

DOI

2018

SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification

DOI

2018

SARAX: A new code for fast reactor analysis part I: Methods

Nuclear Engineering and Design

DOI

2018

A hybrid method to generate few-group cross sections for fast reactor analysis

DOI

2018

Unstructured coarse mesh finite difference method to accelerate k-eigenvalue and fixed source neutron transport calculations

Annals of Nuclear Energy

DOI

2018

Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system

Annals of Nuclear Energy

DOI

2018

Burnable Poison Design for Supercritical Water Cooled Reactor With Annular Fuel

DOI

2018

Transient analysis for liquid‐fuel molten salt reactor based on MOREL2.0 code

DOI

2018

Hybrid MPI-communication for the multi-angular S N parallel sweep on 3-D regular grids

Annals of Nuclear Energy

DOI

2017

《翻译:跨语言和文化的交流》评介

《天津外国语大学学报》

2017

Developments of the sodium fast reactor analysis code SARAX: methods and verification

2017

Improved discrete nodal transport method for treating void regions

DOI

2017

Reactor core transient analysis of an innovative high‐level nuclear waste transmuter with metal fuel

DOI

2017

Effect of high-energy neutron source on predicting the proton beam current in the ADS design

DOI

2017

Leakage reconstruction method for 2D/1D fusion transport calculations

DOI

2017

Assessment of transient characteristics of fast reactors and influences of minor actinides using neutron transport method

DOI

2017

Comparisons of SN and Monte-Carlo methods in PWR ex-core detector response simulation

DOI

2017

Improvements and validation of the transient analysis code MOREL for molten salt reactors

DOI

2017

2D/1D融合輸送計算のための漏れ再構成法【Powered by NICT】

2017

Development of a new parallel SN code for neutron-photon transport calculation in 3-D cylindrical geometry

DOI

2017

A new approach to three-dimensional neutron transport solution based on the method of characteristics and linear axial approximation

Journal of Computational Physics

DOI

2017

Improvement and verification of the fast reactor neutronics code NECP-SARAX

DOI

2017

Application of the virtual density theory in fast reactor analysis based on the neutron transport calculation

DOI

2016

外语教育技术的学科蜕变

《外语教学理论与实践》

2016

溶融池の定常状態物理-熱結合計算に関する研究【JST・京大機械翻訳】

2016

The Generation of Few-Group Constants for Fast Reactor Analysis

DOI

2016

超臨界水性可燃性毒物の設計と分析【JST・京大機械翻訳】

2016

NECP-RIVER: A 3-D nodal SN code for small critical facilities

2016

Boron‐free small modular pressurized water reactor design with new burnable absorber

DOI

2016

Power flattening study of ultra‐long cycle fast reactor using thorium fuel

DOI

2016

Neutronics studies on the feasibility of developing fast breeder reactor with flexible breeding ratio

DOI

2016

Coupled Neutronics and Thermal–Hydraulics Analysis of Annular Fuel Assembly for SCWR

DOI

2015

高校翻译人才培养中几个问题的认识——吕俊教授访谈录

《疯狂英语(双语世界)》

2015

NECP-Cacti: Pressurized Water Reactor lattice code development

2015

Rapid neutron reactor capable of realizing conversion of proliferation and combustion functions

2015

Three-Dimensional Discrete Ordinate Transport Code Based on KBA Method

2015

Economics analysis of fuel cycle cost of fusion–fission hybrid reactors based on different fuel cycle strategies

DOI

2015

Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design

DOI

2015

ICONE23-1692 3D PWR POWER DISTRIBUTION ON-LINE MONITORING BASED ON HARMONICS EXPANSION

DOI

2015

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

DOI

2015

Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport method

DOI

2015

An Improved Resonance Self-Shielding Calculation Method Based on Equivalence Theory

DOI

2014

Burnup calculations of light water-cooled pressure tube blanket for a fusion-fission hybrid reactor

DOI

2014

Preliminary Core Design of the Long Life S-CO2 Cooled Fast Reactor With 300WMth

DOI

2014

LAVENDER: A steady-state core analysis code for design studies of accelerator driven subcritical reactors

Nuclear Engineering and Design

DOI

2014

Pre-conceptual core design of SCWR with annular fuel rods

DOI

2014

Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors

DOI

2014

A deterministic and Monte Carlo coupling method for PWR cavity radiation streaming calculation

Annals of Nuclear Energy

DOI

2014

基于EFEN-SP3方法的高性能全堆芯Pin-by-pin计算研究

2014

Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh

DOI

2013

机助外语教学的计量学考察暨外语教育技术学的发展态势展望

《外语电化教学》，No. 2

下载原文

2013

信息化背景下的外语教师在线专业发展研究

《语文学刊(教育版)》

2013

媒介素养与高校外语教师专业发展研究

《教学研究》

2013

非英语专业教材现状暨第五代教材编写新理念思考——基于教材的外语教师专业发展研究之一

《疯狂英语(双语世界)》

2013

Three-Dimensional Inverse Transport Solver Based on Compressive Sensing Technique

DOI

2013

Study on Improvement of Analytic Depletion Calculation Method

DOI

2013

A code development for LLFP transmutation analysis based on the whole pin-wise calculation in PWRs

DOI

2013

Optimization Study on LLFPs Transmutation in PWRs

DOI

2013

Studies on LLFP transmutation in a pressurized water reactor

DOI

2013

Improved Core Design of SCWR With Double-Row-Rod Assembly

2013

Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation

DOI

2013

Stability analysis of CMFD acceleration for the wavelet expansion method of neutron transport equation

Nuclear Engineering and Design

DOI

2013

Preliminary Conceptual Design of Accelerator Driven Sub-critical System

2013

Equilibrium Cycle Design for LLFPs Transmutation in PWRs

2013

A 3D transport-based core analysis code for research reactors with unstructured geometry

DOI

2013

Study on three-dimensional heterogeneous calculation of ITER test blanket module with deterministic method

DOI

2013

A Neutronics Concept Design of Lead-Bismuth Cooled Accelerator-Driven System for Minor Actinide Transmutation

DOI

2013

Three-Dimensional Core Preliminary Analysis on Breeding Capability of Super Fast Reactor

2013

Spatially Dependent Resonance Cross Sections in a Fuel Plate

DOI

2013

Neutronics analysis of minor actinides transmutation in a fusion-driven subcritical system

DOI

2013

NAPTH: Neutronics analysis code system for the fusion-fission hybrid reactor with pressure tube type blanket

DOI

2013

A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production

DOI

2013

EFEN-SP 3 方法的加速与并行计算研究

2012

国外二语教师认知研究回顾与展望

《西南交通大学学报(社会科学版)》

2012

Research on the Subgroup Method and 2D Arbitrary Geometry Resonance Calculation Code

DOI

2012

The neutronics studies of fusion fission hybrid power reactor

DOI

2012

Economic Evaluation on the MOX Fuel in the Closed Fuel Cycle

DOI

2012

Application of Monte Carlo and discrete ordinate coupling method to pressurized water reactor cavity radiation streaming calculation

DOI

2012

Neutronics Performance of a Fusion-Fission Hybrid Reactor With Pressure Tube Assemblies

DOI

2012

Application of the wavelet expansion method in spatial-angular discretization of the neutron transport equation

DOI

2012

Application of Fine Depletion Calculation for LLFPs In-Core Transmutation Evaluation in PWRs

DOI

2012

The neutronics studies of a fusion fission hybrid reactor using pressure tube blankets

DOI

2012

Calculations of the Dual Functional Lithium Lead-Test Blanket Module for ITER With Three-Dimensional Deterministic Method

DOI

2011

播客技术在外语教育中的应用潜力分析

《中国远程教育》，No. 1

下载原文

2011

英语交际教学法中自主学习策略的应用分析

《长春理工大学学报(社会科学版)》

2011

博洛尼亚进程中的芬兰教师教育改革及其启示

《高教探索》

2010

后大学英语时代基础英语教学战略调整的思考——兼论语言教学向双语教学过渡的接口问题

《沈阳农业大学学报(社会科学版)》

2010

通识教育视角下英语教师专业发展方向及对策研究

《黑龙江教育(高教研究与评估)》

2010

Application of wavelets scaling function expansion method in resonance self-shielding calculation

DOI

2010

Neutron Transport Solution Using the Daubechies’ Wavelets in the Spatial Discretization

DOI

2010

Daubechies’ Wavelet Method for Angular Solution of the Neutron Transport Equation

DOI

2010

The wavelet function expansion method for solving the neutron transport equation - 027

2009

外语教学研究的范式转换

《教育评论》

2009

隐喻指称研究的动态转变——试论语境规约下的隐喻指称意义建构

《疯狂英语(双语世界)》

2009

An improved three-dimensional wavelet-based method for solving the first-order Boltzmann transport equation

DOI

2009

Wavelet-based angular dependence analysis of the heterogeneous calculation on MOX fuel lattice

DOI

2008

非英语专业学生课外无监控网络英语自主学习情况调查

《江西师范大学学报(哲学社会科学版)》，No. 2

下载原文

2008

语块在英语学习者写作语篇中的应用——一项基于语料的对比研究

《长江大学学报(社会科学版)》

2008

Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretization

DOI

2007

惯用语隐喻意义识别的实证研究

《聊城大学学报(社会科学版)》

2006

素雅婉约的女性之歌——曼斯菲尔德的《幸福》与凌叔华的《花之寺》之比较

《怀化学院学报》

2005

浅论曼斯费尔德小说《幸福》中女性幸福感的幻灭

《聊城大学学报(社会科学版)》

2005

词汇语块在语篇中的应用研究

《东南大学》