Published December 2001 | Version v1
Report Open

Generation IV concepts - Presentation at ACRS workshop 'Regulatory challenges for future nuclear power plants'

  • 1. Office of Technology and International Cooperation (United States)

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

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Part of:
Proceedings of the advisory committee on reactor safeguards workshop on future reactors

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)

Optional Information

Secondary number(s)
INIS-XA-N--007