Journal & Publication about Training, Research, Isotopes, General Atomics (TRIGA) Reactors

The TRIGA was developed to be a reactor that was designed to be "safe even in the hands of a young graduate student." GA's reactors are used in many diverse applications, including production of radioisotopes for medicine and industry, treatment of tumors, nondestructive testing, basic research on the properties of matter, and for education and training.

TRIGA is a class of small nuclear reactor designed and manufactured by General Atomics. GA's TRIGA reactor is the most widely used non-power nuclear reactor in the world. GA has sold 66 TRIGA reactors, which are in use or under construction at universities, government and industrial laboratories, and medical centers in 24 countries.

Edward Teller headed a group of young nuclear physicists in San Diego in the summer of 1956 to design a reactor which could not, by its design, suffer from a meltdown. The design was largely the suggestion of Freeman Dyson. The prototype for the TRIGA nuclear reactor (TRIGA Mark I) was commissioned on 3 May 1958 in San Diego and operated until shut down in 1997. It has been designated as a nuclear historic landmark by the American Nuclear Society.

Mark II, Mark III and other variants of the TRIGA design have subsequently been produced, and a total of 35 TRIGA reactors have been installed at locations across the United States. A further 35 reactors have been installed in other countries. Consequently, TRIGA reactors can be found in Austria, Bangladesh, Brazil, Congo, Colombia, Finland, Germany, Indonesia, Italy, Japan, Malaysia, Mexico, Philippines, Puerto Rico, Slovenia, and Vietnam.

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Activity of TRIGA core components : The activity of TRIGA core components was estimated.

Fundamental approach to TRIGA steady-state thermal-hydraulic CHF analysis : Methods are investigated for predicting the power at which critical heat flux (CHF) occurs in TRIGA reactors that rely on natural convection for primary flow.

Calculation of the Activity Inventory for the TRIGA Reactor at the Medical University of Hannover (MHH) in Preparation for Dismantling the Facility : It is planned to dismantle the TRIGA reactor facility at the Medical University of Hannover (MHH). Radioactive waste resulting from this dismantling will be disposed of externally, any remaining materials as well as the building structures will then be measured to ensure there is no residual activity.

A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR : Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor.

Design Verification Report Neutron Radiography Facility (NRF) TRIGA Fuel Storage Systems : This report outlines the methods, procedures, and outputs developed during the Neutron Radiography Facility (NRF) Training, Research and Isotope Production, General Atomics (TRIGA) fuel storage system design and fabrication.

ORIGEN2 calculations supporting TRIGA irradiated fuel data package : ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiography Facility. The calculations support storage and disposal and results include mass, activity,and decay heat.

Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation : Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculated values as a means to validate the reported element burnups. A newly installed and functional gamma-ray detection subsystem of the In-Cell Examination System was used to perform the measurements and is described in some detail.