Concept and design of a supercritical-pressure, direct-cycle light water reactor
Creators
- 1. Univ. of Tokyo, Ibaraki (Japan). Nuclear Engineering Research Lab.
Description
The concept of a supercritical-pressure, direct-cycle light water reactor is presented. Its feasibility is assessed by a study of its neutronic and thermal-hydraulic design. The system pressure is 250 bars. The coolant density decreases continuously in the core, and the coolant is fed directly to the turbines. This eliminates the recirculation system, steam separators, and dryers. The diameter of the reactor pressure vessel is smaller than that of a pressurized water reactor (PWR), and the vessel wall is not very thick despite the high pressure. The required core flow rate is about one-eighth that of a PWR. There are only two coolant loops in a 1,145-MW (electric) reactor, and the turbines are smaller than those of a light water reactor. These features greatly simplify the reactor plant. The thermal efficiency is improved 19% over that of a PWR
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 103
- Journal Issue
- 3
- Journal Page Range
- p. 295-302.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25010703
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRITICAL PRESSURE; DESIGN; EFFICIENCY; HEAT TRANSFER; HYDRAULICS; NEUTRON TRANSPORT; PRESSURE VESSELS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; STEAM TURBINES; SUPERCRITICAL STATE; WATER COOLED REACTORS
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; ENERGY TRANSFER; EQUIPMENT; MACHINERY; NEUTRAL-PARTICLE TRANSPORT; PHYSICAL PROPERTIES; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC PROPERTIES; TURBINES; TURBOMACHINERY