|Date:||7 Jun 2016|
|Time:||6:45-8:00pm (6:30 for registration)|
|Venue:||Lecture Theatre LT-7, Academic Building 1, City University of Hong Kong|
|Organizer(s):||The Hong Kong Nuclear Society|
|Supporter(s):||HKARMS, IOSH (HK), HKIE-NE, HKRPS|
|Speaker:||Lin-wen Hu, PhD, PE, MIT Nuclear Reactor Laboratory|
|Contact Person:||Dr Louis Liu|
|Content:||The Fluoride salt-cooled High-temperature Reactor (FHR) is a new reactor concept that combines a liquid salt coolant and high temperature graphite-matrix coated coated-particle fuel originally developed for High Temperature Gas-cooled Reactors (HTGRs). The base-line liquid salt coolant was originally developed for use in molten salt reactors (MSRs) where the fuel is dissolved in the salt. The FHR operates at low pressure and has excellent heat transfer characteristics with superior safety features. Design temperature of FHR coolant is about 600-700įC that enables a nuclear air-Brayton combined cycle power system adapted from natural gas combined cycle plants. Research and development of FHR is supported by U.S. Department of Energy (DOE) through a joint university program at MIT, University of California-Berkeley, University of Wisconsin-Madison, and University of New Mexico. In China, Shanghai Institute of Applied Physics (SINAP) of Chinese Academy of Sciences (CAS) is leading the FHR development and is planning to build a 10-MW test reactor (TMSR-SF1). A Memorandum of Understanding was signed between U.S. DOE and CAS to cooperate on FHR technology. This talk will provide an overview of selected FHR research and development activities at MIT that includes the materials irradiation tests at the MIT Research Reactor and a pre-conceptual design 10 MW Transportable FHR for off-grid applications.
Dr. Lin-wen Hu received her PhD degree from MIT Nuclear Engineering Department and has more than 20 years of experience in design and safety analysis of nuclear systems and applications of nuclear technology. Dr. Hu is currently the Director for Research and Services and a Principal Research Scientist at the MIT Nuclear Reactor Laboratory (MIT-NRL). Her group carries out research and development that cover a broad range of nuclear technology such as nuclear system design and safety, nuclear materials and fuel irradiation tests, radioisotope production and applications, and nuclear analytical methods. Dr. Hu currently leads research projects in the MITR Low Enrichment Uranium (LEU) conversion study including transitional core conversion strategy and LEU fuel element design, core analysis benchmark and instrumentation design for INLís transient reactor test facility (TREAT), and Fluoride salt-cooled High-temperature (FHR) development including test reactor licensing analysis methodology development, transportable FHR design, and in-pile materials and fluoride salt irradiation tests.
|Remarks:||The event is free to members of organisers and supporting organisations. Enrollment is on a first-come first-served basis. Members register on-line will be acknowledged automatically. Information collected here will be used solely for the administration of this event..
CPD certificate will be issued to members of HKNS and supporting organisations.