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View article: Research Advances on High-Fidelity Neutronics Computational Methods and Applications for Advanced Nuclear Reactors
Research Advances on High-Fidelity Neutronics Computational Methods and Applications for Advanced Nuclear Reactors Open
View article: Implementation of inverse transform sampling method for photon transport in Monte Carlo code and nuclear data library preparation by NECP-Atlas
Implementation of inverse transform sampling method for photon transport in Monte Carlo code and nuclear data library preparation by NECP-Atlas Open
View article: Calculation and analysis of thermal scattering law data of sub-stoichiometric metal hydrides
Calculation and analysis of thermal scattering law data of sub-stoichiometric metal hydrides Open
Metal hydrides are promising moderator materials in advanced reactors, where their thermal neutron scattering cross sections significantly affect the accuracy of reactor design. This study uses special quasi random structure (SQS) and firs…
View article: Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas
Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas Open
The latest evaluated nuclear data libraries, including ENDF/B-VIII.0, TENDL2019, all have two formats, the Evaluated Nuclear Data File (ENDF-6) nuclear data format, and the Generalised Nuclear Database Structure (GNDS) format. The first of…
View article: Generation and analysis of independent fission yield covariances based on GEF model code
Generation and analysis of independent fission yield covariances based on GEF model code Open
The fission yield data provided by the evaluated nuclear data files do not contain covariance information, which is not conducive to uncertainty analysis. To generate covariance information, the model parameters of the code GEF which descr…
View article: Implementation of the RESKR module in NJOY
Implementation of the RESKR module in NJOY Open
The Blackshaw-Murray[1] elastic kernel represents the effect of neutron up-scattering caused by thermal motion of target nuclei and resonance elastic scattering on the multigroup scattering matrices. A first implementation of this model wa…
View article: Impact of the Resonance Elastic Scattering on Reactor-Core Physics Calculation Results Based on the Deterministic Method
Impact of the Resonance Elastic Scattering on Reactor-Core Physics Calculation Results Based on the Deterministic Method Open
View article: Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT
Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT Open
MgF2 as a moderator material has been extensively used in the beam shaping assembly (BSA) that plays an important role in the boron neutron capture therapy (BNCT). Regarded as important for applications, the thermal neutron scattering data…
View article: Burnup Chain Compression Method Preserving Neutronics, Decay Photon Source Term and Decay Heat Calculation Results
Burnup Chain Compression Method Preserving Neutronics, Decay Photon Source Term and Decay Heat Calculation Results Open
View article: Treatments of Thermal Neutron Scattering Data and Their Effect on Neutronics Calculations
Treatments of Thermal Neutron Scattering Data and Their Effect on Neutronics Calculations Open
In the conventional method to generate thermal scattering cross section of moderator materials, only one of the coherent elastic scattering and incoherent elastic scattering is considered in neutronics calculations. For the inelastic scatt…
View article: PROCESSING RESONANCE SELF-SHIELDING EFFECT OF GADOLINIA BASED ON IMPTOVED SUPERCELL SCHEME
PROCESSING RESONANCE SELF-SHIELDING EFFECT OF GADOLINIA BASED ON IMPTOVED SUPERCELL SCHEME Open
An improved supercell scheme has been proposed in this paper to efficiently and accurately process resonance self-shielding effect of gadolinia. Resonance effects are classified into global shadowing effect and local effects involving reso…
View article: METHODS FOR CALCULATION OF SELF-SHIELDED CROSS SECTIONS OF FULLY CERAMIC MICRO-ENCAPSULATED FUEL DOUBLE HETEROGENEOUS SYSTEM
METHODS FOR CALCULATION OF SELF-SHIELDED CROSS SECTIONS OF FULLY CERAMIC MICRO-ENCAPSULATED FUEL DOUBLE HETEROGENEOUS SYSTEM Open
Fully ceramic micro-encapsulated (FCM) fuel is a kind of fuel that employs tri-structural isotropic (TRISO) particles to enhance safety. The FCM fuel assembly is a double heterogeneous system. The conventional self-shielding calculation me…
View article: APPLICATION OF ATHERMAL RECOMBINATION CORRECTED DPA MODEL IN NUCLEAR DATA PROCESSING CODE NECP-ATLAS
APPLICATION OF ATHERMAL RECOMBINATION CORRECTED DPA MODEL IN NUCLEAR DATA PROCESSING CODE NECP-ATLAS Open
The Displacement per Atom (DPA) is an important factor used to quantify the irradiation damage of materials. The radiation damage energy production cross section obtained by nuclear data processing code is an essential nuclear data used to…