Hongchun Wu
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View article: Multi-material laser powder bed fusion of Ti64/AlSi10Mg composites with bionic finger-inserted interface
Multi-material laser powder bed fusion of Ti64/AlSi10Mg composites with bionic finger-inserted interface Open
Inspired by the interdigitated microstructures found in natural biological systems, this study explores the design and additive manufacturing of three-dimensional, multi-material Ti64/AlSi10Mg architectures with enhanced mechanical propert…
View article: Improved positioning criterion and imaging scheme of deep UV planar laser-induced fluorescence technology
Improved positioning criterion and imaging scheme of deep UV planar laser-induced fluorescence technology Open
In summary, we have developed a physical model to describe the evolution of the nitric oxide-based planar laser-induced fluorescence technology (NO-PLIF) signal in a high-enthalpy wind tunnel and analyzed the factors that affect the contra…
View article: A simulation approach for start-up without secondary neutron sources of Hualong One: A Monte-Carlo-deterministic framework
A simulation approach for start-up without secondary neutron sources of Hualong One: A Monte-Carlo-deterministic framework Open
Since secondary neutron sources in Pressurized Water Reactors (PWRs) continuously produce tritium, the technology of replacing these sources with spent fuel assemblies has been proposed to reduce such emissions. To this end, this study int…
View article: Method Research on the Model Optimization of Whole-Core Fuel-Assembly Bowing Based on 3D Variational Algorithm and the Measurement Values
Method Research on the Model Optimization of Whole-Core Fuel-Assembly Bowing Based on 3D Variational Algorithm and the Measurement Values Open
The phenomenon of fuel-assembly bowing would inevitably occur during operation, but the fuel-assembly bowing cannot be measured directly. Therefore, the challenge lies in obtaining the actual fuel-assembly bowing, which is a prerequisite f…
View article: Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor
Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor Open
The Pebble-Bed High Temperature Gas-cooled Reactor (PB-HTGR) is considered one of the most promising next-generation nuclear energy systems. Due to its unique operational characteristics and neutron spectrum, PB-HTGR presents many challeng…
View article: Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX
Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX Open
Two issues arise in the calculation of the multi-group scattering matrix when employing a continuous-energy Monte Carlo code for generating homogenized multi-group cross-sections. Firstly, the analog estimator is used to evaluate group-to-…
View article: A New Conjugate Gradient Method for Impact Load Identification of Stochastic Composite Structures
A New Conjugate Gradient Method for Impact Load Identification of Stochastic Composite Structures Open
This paper presents a novel conjugate gradient method to identify the impact force of stochastic composite structure. Firstly, the proposed method is established based on constructing a new gradient regularization operator, and its stabili…
View article: The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications
The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications Open
This paper presents two new methods for variance reduction for shielding calculation in Monte Carlo radiation transport. One method is CADIS-NEE, which combines Consistent Adjoint Driven Importance Sampling (CADIS) and next-event estimator…
View article: Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method Open
Advanced nuclear reactors, especially the newly developed small and micro-reactors have complex neutron spectrum, which makes the deterministic reactor core calculations sensitive to the energy group structure of few-group cross-sections. …
View article: PWR core calculation based on pin-cell homogenization in three-dimensional pin-by-pin geometry
PWR core calculation based on pin-cell homogenization in three-dimensional pin-by-pin geometry Open
For the pressurized water reactor two-step calculation, the traditional assembly homogenization and two-group neutron diffusion calculation have been widely used. When it comes to the core pin-by-pin simulation, many models and techniques …
View article: Count Rate Analysis of the Source-range Detector for M310
Count Rate Analysis of the Source-range Detector for M310 Open
This paper analyses the count rate of the ex-core source-range detector for Unit 4, M310 Pressurized Water Reactor (PWR), at Fujian Fuqing Nuclear Power Co., Ltd (FQNPC). The analysis encompasses power states during Cycle 1 startup and Cyc…
View article: High-intensity spatial-mode steerable frequency up-converter toward on-chip integration
High-intensity spatial-mode steerable frequency up-converter toward on-chip integration Open
Integrated photonic devices are essential for on-chip optical communication, optical-electronic systems, and quantum information sciences. To develop a high-fidelity interface between photonics in various frequency domains without disturbi…
View article: Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0
Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0 Open
NECP-MCX is a Monte-Carlo particle-transport code developed by the Nuclear Engineering Computational Physics (NECP) Lab. of Xi’an Jiaotong University in 2018. The first version of NECP-MCX is focused on addressing the challenge of deep-pen…
View article: Development of sensitivity calculation capability of Legendre moments of scattering angular distributions in NECP-MCX
Development of sensitivity calculation capability of Legendre moments of scattering angular distributions in NECP-MCX Open
The capability of sensitivity coefficients calculation of keff and reaction rate ratios to Legendre moment of scattering angular distributions based on a fully continuous method has been developed in the Monte Caro code NECP-MCX. The sensi…
View article: The CADIS-DXTRAN method in NECP-MCX for Radiation Shielding Simulations
The CADIS-DXTRAN method in NECP-MCX for Radiation Shielding Simulations Open
This paper discusses the implementation of the Consistent Adjoint-Driven Importance Sampling-Deterministic Transport (CADISDXTRAN) method in NECP-MCX to speed up Monte Carlo simulations for neutron radiation shielding applications. It prov…
View article: A practical subcritical rod worth measurement technique based on the improved neutron source multiplication method
A practical subcritical rod worth measurement technique based on the improved neutron source multiplication method Open
The control rod worth is a key safety parameter required to be measured in commercial pressurized water reactors (PWRs). Conventionally, the control rod worth is measured after reaching the critical state, which occupies the considerable t…
View article: The applicability study and validation of TULIP code for full energy range spectrum
The applicability study and validation of TULIP code for full energy range spectrum Open
NECP-SARAX is a neutronics analysis code system for advanced reactor developed by Nuclear Engineering Computational Physics Laboratory of Xi'an Jiaotong University. In past few years, improvements have been implemented in TULIP code which …
View article: Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX
Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX Open
In the two-step analysis of Pebble-Bed type High-Temperature Gas-Cooled Reactor (PB-HTGR), the lattice physics calculation for the generation of homogenized cross-sections is based on the fuel pebble. However, the randomly-dispersed fuel p…
View article: Supplementary Figure Legend from A Sequence Polymorphism in <i>miR-608</i> Predicts Recurrence after Radiotherapy for Nasopharyngeal Carcinoma
Supplementary Figure Legend from A Sequence Polymorphism in <i>miR-608</i> Predicts Recurrence after Radiotherapy for Nasopharyngeal Carcinoma Open
PDF file - 64K
View article: Supplementary Table 2 from A Sequence Polymorphism in <i>miR-608</i> Predicts Recurrence after Radiotherapy for Nasopharyngeal Carcinoma
Supplementary Table 2 from A Sequence Polymorphism in <i>miR-608</i> Predicts Recurrence after Radiotherapy for Nasopharyngeal Carcinoma Open
PDF file - 79K, Sequence of primers using real time RT-PCR analysis.