Skip Nav Destination
Close Modal
Update search
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
NARROW
Format
Article Type
Subject Area
Topics
Date
Availability
1-20 of 24
Keywords: HTGR
Close
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
1
Sort by
Proceedings Papers
Study on the Effective Diffusion Coefficient of Inert Gases in Porous Graphite Materials
Available to PurchaseRui Nie, Yu Wang, Ziling Zhou, Weihua Zhang, Feng Xie, Hong Li, Liqiang Wei, Zhixiang Fan, Jia Fu, Qunchao Fan
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A042, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135581
... Abstract The high-temperature gas-cooled reactor (HTGR), is globally recognized as one of the reactor types embodying the safety features of the fourth generation, with the advantages of safety, high thermal efficiency in power generation, a small emergency planning zone, and the ability to use...
Proceedings Papers
Research on Fuel Pebble Modeling Methods Comparison and Eigenvalue Analysis of the Running-in Phase of HTR-PM
Available to Purchase
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131880
... into fuel pebble homogenization and support the feasibility of applying proper fuel pebble modeling to full-core HTR design and simulation. advanced reactor fuel design HTGR neutronics safety Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024...
Proceedings Papers
Isotopic Measurement of HTR-10 Irradiated Fuels Based on Anti-Compton Gamma Spectroscopic Method
Available to Purchase
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132758
... Abstract Accurate determination of isotopic compositions of irradiated fuel elements plays a critical role in assessing fuel burnup, optimizing reactor performance, and ensuring safe operations. Spherical fuel elements are used in pebble-bed HTGRs (High Temperature Gas-cooled Reactors...
Proceedings Papers
CFD-DEM Simulation on Gas-Solid Separation and Sphere Packing Behaviors in a Storage Bin of the Small Absorber Sphere System
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A054, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135598
... Abstract The small absorber spheres system is one kind of shutdown system in the pebble-bed High Temperature Gas-cooled Reactor (HTGR or HTR). Vertical pneumatic conveying of small absorber spheres in pebble-bed HTGR is a special application of pneumatic conveying technique. The whole process...
Proceedings Papers
Methodology Development for Explosion Hazard Evaluation in Hydrogen Production System Using High Temperature Gas-Cooled Reactor
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A050, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135407
... Abstract High temperature gas-cooled reactor (HTGR) is expected to use nuclear heat to wide range of industrial applications such as hydrogen production due to its high temperature heat supply capability and inherent safe characteristics. One of the key technologies is a safety evaluation...
Proceedings Papers
A Preliminary Thermodynamic Model of Hydrogen Generation Using Solid Oxide Electrolysis Cell (SOEC) Coupled With a High-Temperature Gas-Cooled Reactor
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A049, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135353
...-temperature gas-cooled reactor (HTGR), it is necessary to assess the technical feasibility of various hydrogen production processes coupled with a HTGR. In this paper, several promising hydrogen production methods were compared from the perspectives of technological maturity, economic viability, and coupling...
Proceedings Papers
Conduct a Tritium Radiation Safety Assessment on the Heating System Directly Supplied by the Steam From the Secondary Loop of the High-Temperature Gas-Cooled Reactor
Available to Purchase
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132181
... Abstract With the increasingly urgent demand for industrial heating, traditional heating methods are no longer suitable for the current energy development situation. The High Temperature Gas-cooled Reactor (HTGR), as a fourth-generation advanced nuclear energy technology, has several advantages...
Proceedings Papers
CFD Simulations of Helium Flow Through Partial Heating Pebble Bed
Available to Purchase
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A061, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135126
... Abstract The modular high temperature gas-cooled reactor (HTGR) is an advanced technology of inherent safety, high electricity generation efficiency, and potential process heat applications in the chemical industry. The packed pebble bed in HTGR consists of a large number of randomly...
Proceedings Papers
Time-Domain Nonlinear Investigation of Two-Phase Flow Instability in HTGR OTSG Using SIMULINK
Available to Purchase
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132493
... Abstract Two-phase flow instability may occur in the once-through steam generator (OTSG) of High-Temperature Gas-cooled Reactors (HTGR). A time-domain theoretical model of HTGR OTSG was established to investigate this phenomenon. The heat transfer tube of OTSG was divided into three regions...
Proceedings Papers
Study on Radionuclide Desorption in Matrix Graphite Under Accident Conditions
Available to Purchase
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A088, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135804
... Abstract High temperature gas cooled reactor (HTGR) is one of the promising advanced nuclear reactor for future electricity generation. The spherical fuel element with thousands of TRISO-coated particles dispersed in the graphite matrix are adopted by the HTGR, which is an important guarantee...
Proceedings Papers
Reconstruction of 3D Nuclear Graphite Based on Generative Adversarial Neural Networks With Gradient Penalty
Available to Purchase
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A036, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134733
... statistics, pore distribution, porosity and specific surface area. The results show the reconstructed graphites are consistent with the original graphite, which proves the reliability of this method. HTGR nuclear grade graphite generative adversarial neural networks Proceedings of the 2024 31st...
Proceedings Papers
Preparation Method of ORIGEN2 Library for High Temperature Gas-Cooled Reactors
Available to PurchaseIrwan Liapto Simanullang, Katsuki Fukuhara, Keisuke Morita, Yuji Fukaya, Hai Quan Ho, Satoru Nagasumi, Kazuhiko Iigaki, Etsuo Ishitsuka, Nozomu Fujimoto
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A023, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90802
... Abstract The ORIGEN2 code has been used for fuel depletion calculations of many kinds of reactor fuels but there is no library for high temperature gas cooled reactors (HTGRs). A set of the ORIGEN2 library for the HTGR has been established to evaluate the fuel burnup characteristics...
Topics:
Very high temperature reactors
Proceedings Papers
Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break
Available to Purchase
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88852
... Abstract Analysis and understanding the depressurization response of the HTGR reactor is essential to the understanding of accident scenarios and design of these reactors. The 350MWe GA-MHTR was used as reference reactor for the current design of the test facility. The design of the test...
Proceedings Papers
Study on Dehumidification of Carbon Materials Based on Thermogravimetry
Available to Purchase
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63633
... at high temperatures in HTGR. In order to reduce the corrosion of impurities on carbon materials, the HTGR core must be dehumidified before it operats. In this paper, the dehumidification of HTGR is taken as the research background. On the one hand, microscopic geometric parameters such as pore size...
Proceedings Papers
Development of Cesium Trap Material for Coated Fuel Particles in High Temperature Gas-Cooled Reactors
Available to Purchase
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61765
... Abstract Cs-Bi and Cs-Sb absorbed graphite samples (Cs-Bi/graphite and Cs-Sb/graphite) were synthesized and their high temperature chemical stabilities were tested up to 1500 °C by TG and analyzed by TEM-EDS for the development of Cs trap material in high temperature gas-cooled reactor (HTGR...
Proceedings Papers
Manufacturability Estimation on Burnable Poison Mixed Fuel For Improving Criticality Safety of HTGR Fuel Fabrication
Available to Purchase
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61763
... Abstract Manufacturability of the BP-mixed uranium dioxide (UO 2 ) kernel for burnable poison (BP) credit concept was estimated to ensure criticality safety in 14 wt% enrichment fuel fabrication facility for commercial high temperature gas-cooled reactor (HTGR). The case of the coating process...
Proceedings Papers
Transport Behavior of Silver in High-Temperature Gas-Cooled Reactors
Available to Purchase
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A013, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63484
... Abstract High-temperature gas-cooled reactor (HTGR) is characterized by inherent safety, superior proliferation resistance, and high efficiency, with a promising prospect on electric power product and high-temperature heat and hydrogen production. The enhanced safety mostly relies on the good...
Proceedings Papers
Heat Transfer Analysis of a Conceptual Horizontally-Oriented High Temperature Gas-Cooled Reactor
Available to PurchaseJinyong Feng, Enrique Velez Lopez, William Robb Stewart, Ralph Wiser, Emilio Baglietto, Koroush Shirvan
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A017, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65828
..., Ralph Wiser1,2, Emilio Baglietto1, Koroush Shirvan1 1Massachusetts Institute of Technology, Cambridge, MA 2MIGHTR LLC, Boston, MA ABSTRACT 1. INTRODUCTION High temperature gas-cooled reactors (HTGRs) have been Gas-cooled reactors have a long history and are in use today. constructed around the world...
Proceedings Papers
Study on Heating Process of Dehumidifying Experiment in HTGR
Available to Purchase
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16358
...Study on Heating Process of Dehumidifying Experiment in HTGR Kaiyue Shen, Wei Zheng, Shengchao Ma, Huaqiang Yin, Xuedong He,Tao Ma Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering...
Proceedings Papers
Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor
Available to Purchase
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A001, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16050
... Abstract The present study aims to propose a guidance that facilitates to determine fuel design limits of commercial HTGR on the basis of licensing experience through the high temperature engineering test reactor (HTTR) construction. The guidance consists of a set of figure of merits (FOMs...
1