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 20
Keywords: high temperature gas-cooled reactor
Close
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Sort by
Proceedings Papers
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91761
... Abstract High temperature gas-cooled reactor (HTGR) has a potential to produce competitive and large amount of carbon-free hydrogen because of its capability to supply high temperature heat of nuclear energy. It is required to establish the control method and system for the HTGR hydrogen...
Proceedings Papers
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A015, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91628
... Abstract The high temperature gas-cooled reactor (HTGR) is an advanced reactor type with safety characteristics of Generation IV nuclear energy systems. In the design process of an HTGR, thermal-hydraulic analysis is of great significance. This paper reviews existing methods for thermal...
Proceedings Papers
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88883
... the development of high-temperature gas-cooled reactors (HTGRs). In this study, we investigated the state of fuel element damage monitoring technology in HTGRs and pressurized water reactors (PWRs), summarized their characteristics and parameters, and compared their advantages and disadvantages. The radioactive...
Proceedings Papers
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A084, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92197
... to the differences between high temperature gas-cooled reactor (HTR) and LWR in core type and accident process, the determination OILs will also be different. This paper conducts the application of method in ERP-NPP-OILs (2017) to HTR especially for OIL1 and OIL2, which is mainly focuses on the “ground” scenario...
Proceedings Papers
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A057, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91754
... Abstract The two-dimensional (2D) system analysis codes are usually used to design and analyze the modular pebble-bed High Temperature Gas-cooled Reactors (HTR). However, in some cases, three-dimensional (3D) characteristics, for example the 3D power distribution and temperature distribution...
Proceedings Papers
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91275
.... The diffusion behavior of tritium in several materials with and without oxide layer is discussed in detail. The oxide layer is more important than intrinsic permeability to prevent tritium permeation. As tritium is the only radioactive source term in the secondary loop of high temperature gas-cooled reactors...
Proceedings Papers
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, V001T02A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63659
... Abstract The trace number of impurities such as CO, H 2 , H 2 O, and CH 4 , which existed in the primary coolant of High Temperature Gas-Cooled Reactor (HTGR), has an adverse effect on the structural metallic materials at elevated temperatures. Mainly, it includes oxidation, decarburization...
Proceedings Papers
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16196
... Abstract A core of the prismatic high temperature gas-cooled reactor (HTGR) consists of fuel blocks, control rod guide blocks and replaceable reflector blocks with surrounding permanent reflector blocks. The core flowrate available for effective cooling of fuels, fuel blocks and control rod...
Proceedings Papers
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16199
... Abstract In the thermal hydraulic design of the prismatic-type of the high temperature gas cooled reactor (HTGR), unintended flows such as gap flows between columns, cross flows between column layers and gap flows between permanent reflectors should be analyzed to minimizing the unintended...
Proceedings Papers
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A005, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16218
... power-level control of high temperature gas-cooled reactor (HTGR) is proposed by only regulating primary helium flowrate, which can be able to provide globally asymptotical closed-loop stability. This new HTGR power-level control is composed by a helium temperature controller and a neutron flux...
Proceedings Papers
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A057, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16839
... The resuspension rate of graphite dust in steam generator of high temperature gas-cooled reactors (HTRs) is calculated both in theoretical Rock’n’Roll model and imperial model derived from precious experiments. Dust diameter, friction velocity, as well as roughness of wall is investigated...
Proceedings Papers
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 175-179, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55008
... is in a range of 0.82∼1.27 MPa.m 1/2 , with an averaged value of 1.038 MPa.m 1/2 . IG-11 graphite fracture toughness high temperature gas-cooled reactor 1 Copyright © 2012 by ASME AN EXPERIMENTAL STUDY ON FRACTURE TOUGHNESS OF A FINE-GRAINED ISOTROPIC GRAPHITE Hongtao WANG Institute of Nuclear...
Proceedings Papers
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 243-248, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54041
... One of the most important properties of the modular high temperature gas-cooled reactor is that the decay heat in the core can be carried out solely by means of passive physical mechanism after shutdown due to accidents. The maximum fuel temperature is guaranteed not to exceed the design...
Proceedings Papers
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 337-343, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29038
... 08 04 2011 Reactivity accident due to inadvertent withdrawal of the control rod is one kind of the design basis accident for high temperature gas-cooled reactors, which should be analyzed carefully in order to validate the reactor inherent safety properties. Based on the preliminary...
Proceedings Papers
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 517-525, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29344
... 08 04 2011 High temperature gas-cooled reactor with direct helium turbine cycle is based on the closed Brayton cycle. Its outstanding feature is the high efficiency of power generation. Pervious researches showed that recuperator was the key component to promote the cycle’s efficiency...
Proceedings Papers
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 793-801, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29820
... 08 04 2011 An Adaptive Unbalance Vibration Control (AUVC) method is studied based on the flexible active magnetic bearing-rotor experimental system AMB-PII, which is built up to simulate the helium turbo compressor rotor of the 10MW high temperature gas-cooled reactor with direct cycle...
Proceedings Papers
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 331-339, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75078
... 25 02 2010 Water-ingress accident, caused by the steam generator heating tube rupture of a high temperature gas-cooled reactor, will introduce a positive reactivity to lead the nuclear power increase rapidly, as well as the chemical reaction of graphite fuel elements and reflector...
Proceedings Papers
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 659-666, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48218
... Recuperator is one of the key components in the helium-turbine cycle coupled with High Temperature Gas cooled Reactor (HTGR). Synthetically considering the heat transfer coefficients, the pressure drop and installation space of recuperator, it is obviously a trend to use compact heat exchanger...
Proceedings Papers
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 185-191, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49527
... the design and operational characteristics of the HTR-10, and can also provide online supports for operators in the main control room, or as a convenient powerful tool for the control system design. High temperature gas-cooled reactor Simulation system Control system design Online support Network...
Proceedings Papers
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 507-513, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89169
... 17 09 2008 The High Temperature Gas-cooled Reactor coupled with gas turbine (HTGR-GT) is supposed to be one of the candidates for the future nuclear power plants in both electricity and hydrogen production. The HTGR-GT cycle is theoretically based on the closed Brayton cycle...