A HAZARDS SUMMARY OF THE PROPOSED RESEARCH AND TRAINING REACTOR

Technical Report · Sun Jan 01 04:00:00 EST 1956

OSTI ID:4335000

Quarles, L R; Walker, W P

The proposed reactor is of the proven pool type design, using highly enriched fuel plates with light water as the moderator, reflector, and coolant. The reactor will operate up to power levels of 100 kw with convection cooling only, employing forced circulation from 100 kw to its maximum power level of 1 Mw. Neutron fluxes of the order of 20/sup 13/ neutrons/cm/sup 2/-sec are obtained at its maximum power level. For purposes of evaluation of the safety and adequacy of the design, a description of the facility, its site, major components, and normal operation, is included in this report. Sufficient climatological, hydrological, geological, and seismological data are presented for evaluating measures taken to protect the public from possible radioactive hazards. The hazard analysis shows that should the maximum assumed accident occur, evacuation of downwind personnel for several miles would be necessary; however, the intensity is sufficiently low to afford adequate time to accomplish this without exposing personnel to serious levels of radiation. It is not believed that any known mechanism could bring: about this maximum assumed accident. (auth)

• Research Organization: Virginia. Univ., Charlottesville. School of Engineering
• NSA Number: NSA-12-012744
• OSTI ID: 4335000
• Report Number(s): UVAR-3 and Amendment
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ACCIDENTS
ATMOSPHERE
CONTAMINATION
CONVECTION
COOLANT LOOPS
ENVIRONMENT
FISSION PRODUCTS
FUEL ELEMENTS
GEOLOGY
HYDROLOGY
MECHANICAL STRUCTURES
NEUTRON FLUX
OPERATION
PERSONNEL
PHYSICS
PLANNING
PLATES
POPULATIONS
PUMPS
RADIATION DOSES
RADIATION PROTECTION
REACTOR CORE
REACTOR SAFETY
REFLECTORS
RESEARCH REACTORS
SEISMOLOGY
WATER COOLANT
WATER MODERATOR
WIND