Published 2006 | Version v1
Book Metadata-only

Reactor Analysis for Counter-Flowing Moderator and Coolant in a Supercritical Water Reactor

Creators

  • 1. University of Wisconsin at Madison, 419 ERB 1500 Engineering Dr Madison, WI 53706 (United States)

Description

New thermal-hydraulic models have been implemented in the PARCS v2.5 core simulator to enable the simulation of heat transfer between the counter-flowing moderator and coolant in supercritical water reactors. The impact of this heat transfer on the performance of an individual assembly has been demonstrated. A quarter-core model has been simulated to demonstrate how this new capability can be used to identify hot channels in the core and to design different core configurations that may reduce the hot channel effects. Future developments will couple this core simulator capability to advanced thermal-hydraulic simulation capability for full core design and transient simulation. (authors)

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers - ASME
Imprint Place
New York (United States)
Imprint Pagination
8 p.

Conference

Title
14. international conference on nuclear engineering (ICONE 14)
Dates
17-20 Jul 2006
Place
Miami, FL (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
39019450
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONFIGURATION; COOLANTS; DESIGN; HEAT TRANSFER; HOT CHANNEL; MODERATORS; PERFORMANCE; SIMULATION; SIMULATORS; THERMAL HYDRAULICS; TRANSIENTS; WATER; WATER MODERATED REACTORS
Descriptors DEC
ANALOG SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; FUNCTIONAL MODELS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; REACTORS