Generation IV concepts - Presentation at ACRS workshop 'Regulatory challenges for future nuclear power plants'
Description
The concept of the Near-Term Deployment Working Group was to define a technical approach for Generation IV system with enough detail to allow evaluation against the goal, bur broad enough to allow for optional features and trade. The following concepts were taken into account: water coolant (water or heavy water), gas coolant, liquid metal coolants. Concepts were grouped according to concept sets of technology base share and design approach. Water coolant concepts were grouped as follows: PWR loop reactors, integral primary system PWRs, Integral BWRs, pressure tube reactors, high conversion cores, supercritical water reactors, advanced fuel cycle concepts. Gas coolant concepts were grouped as follows: pebble bed modular reactors; prismatic modular reactors, very high temperature reactors, fast spectrum reactors, others (fluidized bed, moving ignition zone concept). Liquid metal concepts were grouped in four major categories: Medium-to-large oxide-fueled systems; Medium-sized metal-fueled systems; Medium-sized Pb/Pb-Bi systems; Small-sized Pb/Pb-Bi systems. The three supporting technology areas were examined: Fuels (oxide, metal, nitride); Coolants (Na, Pb/Pb-Bi); Fuel Cycle (advanced aqueous, pyroprocess). Non-classical concepts were also grouped as follows: Eutectic metallic fuel; Molten salt fuel; Gas core reactor; Molten salt cooled/solid fuel; Organic cooled reactor; Solid conduction/heat pipe; Fission product direct energy conversion. The Technical working Groups are analyzing the candidate concepts for performance potential relative to the goals; and technology gaps
Files
35050479.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the advisory committee on reactor safeguards workshop on future reactors
- Imprint Pagination
- 340 p.
- Journal Page Range
- p. 39-47
- Report number
- NUREG/CP--0175
Conference
- Title
- Advisory committee on reactor safeguards workshop on future reactors
- Dates
- 4-5 Jun 2001
- Place
- Rockville, MD (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35050479
- Subject category
- S29: ENERGY PLANNING, POLICY AND ECONOMY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; DUAL-PURPOSE POWER PLANTS; FAST REACTORS; FUEL CYCLE; GAS COOLED REACTORS; HEAVY WATER COOLED REACTORS; HTGR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LIQUID METALS; MOLTEN SALT COOLED REACTORS; MOLTEN SALT FUELED REACTORS; OPTIMIZATION; ORGANIC COOLED REACTORS; PEBBLE BED REACTORS; PRESSURE TUBE REACTORS; PWR TYPE REACTORS; TECHNOLOGY ASSESSMENT; URANIUM NITRIDES; URANIUM OXIDES; WATER COOLED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FLUID FUELED REACTORS; FLUIDS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUIDS; METALS; MOLTEN SALT REACTORS; NITRIDES; NITROGEN COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PNICTIDES; POWER PLANTS; POWER REACTORS; REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- INIS-XA-N--007