TRIGA research reactor activities around the world
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5036305
- General Atomics, San Diego, CA (United States)
Recent activities at several overseas TRIGA installations are discussed in this paper, including reactor performance, research programs under way, and plans for future upgrades. The following installations are included: (1) 14,000-kW TRIGA at the Institute for Nuclear Research, Pitesti, Romania; (2) 2,000-kW TRIGA Mark II at the Institute of Nuclear Technology, Dhaka, Bangladesh; (3) 3,000-kW TRIGA conversion, Philippine Nuclear Research Institute, Quezon City, Philippines; and (4) other ongoing installations, including a 1,500-kW TRIGA Mark II at Rabat, Morocco, and a 1,000-kW conversion/upgrade at the Institute Asunto Nucleares, Bogota, Columbia.
- OSTI ID:
- 5036305
- Report Number(s):
- CONF-911107-; CODEN: TANSA
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 64; Conference: 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics, San Francisco, CA (United States), 10-15 Nov 1991; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
TRIGA TYPE REACTORS
RESEARCH PROGRAMS
BANGLADESH
BURNUP
COLOMBIA
DOPED MATERIALS
ECCS
FUEL ELEMENTS
IAEA
ISOTOPE PRODUCTION
LOSS OF FLOW
MATERIALS TESTING
NATURAL CONVECTION
NEUTRON ACTIVATION ANALYSIS
NEUTRON RADIOGRAPHY
PHILIPPINES
POST-IRRADIATION EXAMINATION
PRR-1 REACTOR
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
ROMANIA
SCATTERING
SILICON
SLIGHTLY ENRICHED URANIUM
STEADY-STATE CONDITIONS
TRAINING
ACCIDENTS
ACTINIDES
ACTIVATION ANALYSIS
ASIA
CHEMICAL ANALYSIS
CONVECTION
DEVELOPING COUNTRIES
EDUCATION
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
EUROPE
HEAT TRANSFER
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
INDUSTRIAL RADIOGRAPHY
INTERNATIONAL ORGANIZATIONS
ISLANDS
ISOTOPE ENRICHED MATERIALS
LATIN AMERICA
MASS TRANSFER
MATERIALS
METALS
OPERATION
POOL TYPE REACTORS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SEMIMETALS
SOLID HOMOGENEOUS REACTORS
SOUTH AMERICA
TESTING
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
TRIGA TYPE REACTORS
RESEARCH PROGRAMS
BANGLADESH
BURNUP
COLOMBIA
DOPED MATERIALS
ECCS
FUEL ELEMENTS
IAEA
ISOTOPE PRODUCTION
LOSS OF FLOW
MATERIALS TESTING
NATURAL CONVECTION
NEUTRON ACTIVATION ANALYSIS
NEUTRON RADIOGRAPHY
PHILIPPINES
POST-IRRADIATION EXAMINATION
PRR-1 REACTOR
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
ROMANIA
SCATTERING
SILICON
SLIGHTLY ENRICHED URANIUM
STEADY-STATE CONDITIONS
TRAINING
ACCIDENTS
ACTINIDES
ACTIVATION ANALYSIS
ASIA
CHEMICAL ANALYSIS
CONVECTION
DEVELOPING COUNTRIES
EDUCATION
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
EUROPE
HEAT TRANSFER
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
INDUSTRIAL RADIOGRAPHY
INTERNATIONAL ORGANIZATIONS
ISLANDS
ISOTOPE ENRICHED MATERIALS
LATIN AMERICA
MASS TRANSFER
MATERIALS
METALS
OPERATION
POOL TYPE REACTORS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SEMIMETALS
SOLID HOMOGENEOUS REACTORS
SOUTH AMERICA
TESTING
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors