ORNL R and D on advanced small and medium power reactors: Selected topics
From 1984-1985, ORNL studied several innovative small and medium power nuclear concepts with respect to viability. Criteria for assessment of market attractiveness were developed and are described here. Using these criteria and descriptions of selected advanced reactor concepts, and assessment of their projected market viability in the time period 2000-2010 was made. All of these selected concepts could be considered as having the potential for meeting the criteria but, in most cases, considerable RandD would be required to reduce uncertainties. This work and later studies of safety and licensing of advanced, passively safe reactor concepts by ORNL are described. The results of these studies are taken into account in most of the current (FY 1989) work at ORNL on advanced reactors. A brief outline of this current work is given. One of the current RandD efforts at ORNL which addresses the operability and safety of advanced reactors is the Advanced Controls Program. Selected topics from this Program are described. 13 refs., 1 fig.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Resource Relation:
- Conference: 16. water reactor safety information meeting, Gaithersburg, MD, USA, 24 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Research Org:
- Oak Ridge National Lab., TN (USA)
- Country of Publication:
- United States
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; MARKETING; HTGR TYPE REACTORS; LMFBR TYPE REACTORS; PWR TYPE REACTORS; COMPUTERIZED CONTROL SYSTEMS; DESIGN; ECONOMICS; FUEL ELEMENTS; GRAPHITE; NUCLEAR POWER PLANTS; PUBLIC HEALTH; PUBLIC OPINION; REACTOR INSTRUMENTATION; REACTOR MATERIALS; REACTOR SAFETY; ROBOTS; SHIELDING; BREEDER REACTORS; CARBON; CONTROL SYSTEMS; ELEMENTAL MINERALS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; MATERIALS; MINERALS; NONMETALS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL POWER PLANTS; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 220400 -- Nuclear Reactor Technology-- Control Systems; 210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 210300 -- Power Reactors, Nonbreeding, Graphite Moderated; 210500 -- Power Reactors, Breeding
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