Lin-Wen Hu
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View article: STAT7 v1.2 User Guide: The STAT7 Code for Statistical Propagation of Uncertainties in Steady-State Thermal Hydraulics Analysis of Plate-Fueled Reactors
STAT7 v1.2 User Guide: The STAT7 Code for Statistical Propagation of Uncertainties in Steady-State Thermal Hydraulics Analysis of Plate-Fueled Reactors Open
The STAT7 software was developed to perform steady-state, single-phase thermal hydraulics analysis of plate-fueled reactors based on statistical propagation of uncertainties. Application of the software is for non-power research and test r…
View article: Tetris-inspired detector with neural network for radiation mapping
Tetris-inspired detector with neural network for radiation mapping Open
View article: Initial Irradiation Tests on the TCR Fuel Form at MIT Nuclear Reactor Laboratory
Initial Irradiation Tests on the TCR Fuel Form at MIT Nuclear Reactor Laboratory Open
View article: Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Preliminary Design
Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Preliminary Design Open
As part of the U.S. National Nuclear Security Administration’s (NNSA) mission to minimize the civilian use of weapon-grade highly enriched uranium (HEU) fuels, the NNSA Office of Material Management and Minimization Conversion Program is c…
View article: Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity
Numerical Simulations of Flow-Induced Deflections in MITR LEU Fuel Plate Due to Channel Size Disparity Open
The hydromechanical stability of the fuel plates in parallel coolant channels of a Materials Testing Reactor (MTR) fuel element design is of great importance to the safety of research and test reactors. Previous analytical, experimental, a…
View article: Tetris-inspired detector with neural network for radiation mapping
Tetris-inspired detector with neural network for radiation mapping Open
In recent years, radiation mapping has attracted widespread research attention and increased public concerns on environmental monitoring. In terms of both materials and their configurations, radiation detectors have been developed to locat…
View article: The STAT7 Code for Statistical Propagation of Uncertainties in Steady State Thermal Hydraulics Analysis of Plate Fueled Reactors
The STAT7 Code for Statistical Propagation of Uncertainties in Steady State Thermal Hydraulics Analysis of Plate Fueled Reactors Open
The STAT7 software was developed to perform steady-state thermal hydraulic analyses. Application of the software is for non-power research and test reactors, including conversion to low-enriched uranium fuel of U.S. High-Performance Resear…
View article: Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Conceptual Design
Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Conceptual Design Open
As part of the U.S. National Nuclear Security Administration’s (NNSA’s) mission to minimize the civilian use of weapon-grade highly enriched uranium (HEU) fuels, the NNSA Office of Material Management and Minimization (M3) Conve…
View article: Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Conceptual Design – Hydraulic Reactor Design Parameters
Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Conceptual Design – Hydraulic Reactor Design Parameters Open
The Massachusetts Institute of Technology Reactor (MITR-II, also referred to as MITR) is one of six U.S. high performance research reactors (USHPRR), including one critical facility, that is actively collaborating with the U.S. National Nu…
View article: MITR Low-Enriched Uranium Conversion Fluid-Structure Interaction Preliminary Design Verification
MITR Low-Enriched Uranium Conversion Fluid-Structure Interaction Preliminary Design Verification Open
The U.S. National Nuclear Security Administration (NNSA) Office of Material Management and Minimization (M3) has developed and is pursuing an integrated approach to address the persistent threat posed by unintentional proliferat…
View article: Tritium generation, release, and retention from in-core fluoride salt irradiations
Tritium generation, release, and retention from in-core fluoride salt irradiations Open
View article: Transitional cores and fuel cycle analyses in support of MIT reactor low enriched uranium fuel conversion
Transitional cores and fuel cycle analyses in support of MIT reactor low enriched uranium fuel conversion Open
View article: Thermal-hydraulic analyses of MIT reactor LEU transition cycles
Thermal-hydraulic analyses of MIT reactor LEU transition cycles Open
View article: Experimental investigation of alumina coating as tritium permeation barrier for molten salt nuclear reactors
Experimental investigation of alumina coating as tritium permeation barrier for molten salt nuclear reactors Open
View article: Computational and Experimental Benchmarking for Transient Fuel Testing
Computational and Experimental Benchmarking for Transient Fuel Testing Open
In 2018 the Transient Reactor Test (TREAT) Facility was restarted. This now-operational facility brings back world-class transient fuel testing capabilities to the U.S. Among a number of parallel efforts prior to the TREAT Facility’s resta…
View article: Integrated FHR technology development: Tritium management, materials testing, salt chemistry control, thermal hydraulics and neutronics, associated benchmarking and commercial basis
Integrated FHR technology development: Tritium management, materials testing, salt chemistry control, thermal hydraulics and neutronics, associated benchmarking and commercial basis Open
This report summarizes the results of a 3-year Integrated Research Project (IRP) sponsored by the U.S. Department of Energy to address major technical challenges in the development of the Fluoride-salt-cooled High-temperature Reactor (FHR)…
View article: Radiation resistant fiber Bragg grating in random air-line fibers for sensing applications in nuclear reactor cores
Radiation resistant fiber Bragg grating in random air-line fibers for sensing applications in nuclear reactor cores Open
This paper reports the testing results of radiation resistant fiber Bragg grating (FBG) in random air-line (RAL) fibers in comparison with FBGs in other radiation-hardened fibers. FBGs in RAL fibers were fabricated by 80 fs ultrafast laser…
View article: Machine learning based system performance prediction model for reactor control
Machine learning based system performance prediction model for reactor control Open
View article: Fluoride salt coolant properties for nuclear reactor applications: A review
Fluoride salt coolant properties for nuclear reactor applications: A review Open
View article: Estimate of radiation release from MIT reactor with un-finned LEU core during Maximum Hypothetical Accident
Estimate of radiation release from MIT reactor with un-finned LEU core during Maximum Hypothetical Accident Open
View article: The STAT7 Code for Statistical Propagation of Uncertainties In Steady-State Thermal Hydraulics Analysis of Plate-Fueled Reactors
The STAT7 Code for Statistical Propagation of Uncertainties In Steady-State Thermal Hydraulics Analysis of Plate-Fueled Reactors Open
The STAT code was written to automate many of the steady-state thermal hydraulic safety calculations for the MIT research reactor, both for conversion of the reactor from high enrichment uranium fuel to low enrichment uranium fuel and for …
View article: Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel
Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel Open
The onset of nucleate boiling (ONB) serves as the thermal-hydraulic operating limit for many research and test reactors. However, boiling incipience under forced convection has not been well-characterized in narrow channel geometries or fo…
View article: Convective Heat Transfer in a High Aspect Ratio Minichannel Heated on One Side
Convective Heat Transfer in a High Aspect Ratio Minichannel Heated on One Side Open
Experimental results are presented for single-phase heat transfer in a narrow rectangular minichannel heated on one side. The aspect ratio and gap thickness of the test channel were 29:1 and 1.96 mm, respectively. Friction pressure drop an…
View article: Convective Heat Transfer in a High Aspect Ratio Minichannel Heated on One Side
Convective Heat Transfer in a High Aspect Ratio Minichannel Heated on One Side Open
Experimental results are presented for single-phase heat transfer in a narrow rectangular minichannel heated on one side. The aspect ratio and gap thickness of the test channel were 29:1 and 1.96 mm, respectively. Friction pressure drop an…
View article: Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat
Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat Open
In 2011 the U.S. Department of Energy through its Nuclear Energy University Program (NEUP) awarded a 3- year integrated research project (IRP) to the Massachusetts Institute of Technology (MIT) and its partners at the University of Califor…