Published January 30, 2007 | Version v1
Journal article

Ex-Core CFD Analysis Results for the Prometheus Gas Reactor

  • 1. Space Engineering, Bechtel Bettis, Inc. West Mifflin, PA 15122 (United States)

Description

This paper presents the initial nozzle-to-nozzle (N2N) reactor vessel model scoping studies using computational fluid dynamics (CFD) analysis methods. The N2N model has been solved under a variety of different boundary conditions. This paper presents some of the basic hydraulic results from the N2N CFD analysis effort. It also demonstrates how designers were going to apply the analysis results to modify a number of the design features. The initial goals for developing a preliminary CFD N2N model were to establish baseline expectations for pressure drops and flow fields around the reactor core. Analysis results indicated that the averaged reactor vessel pressure drop for all analyzed cases was 46.9 kPa (∼6.8 psid). In addition, mass flow distributions to the three core fuel channel regions exhibited a nearly inverted profile to those specified for the in-core thermal/hydraulic design. During subsequent design iterations, the goal would have been to modify or add design features that would have minimized reactor vessel pressure drop and improved flow distribution to the inlet of the core

Additional details

Identifiers

Publishing Information

Journal Title
AIP Conference Proceedings
Journal Volume
880
Journal Issue
1
Journal Page Range
p. 551-558
ISSN
0094-243X
CODEN
APCPCS

Conference

Title
11. conference on thermophysics applications in microgravity; 24. symposium on space nuclear power and propulsion; 5. conference on human/robotic technology and the vision for space exploration; 5. symposium on space colonization; 4. symposium on new frontiers and future concepts
Acronym
International forum-STAIF 2007
Dates
11-15 Feb 2007
Place
Albuquerque, NM (United States)

INIS

Country of Publication
United States
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39071556
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOUNDARY CONDITIONS; COMPUTERIZED SIMULATION; DESIGN; DISTRIBUTION; FISSION; FLUID MECHANICS; NUCLEAR FUELS; PRESSURE DROP; PROPULSION; REACTOR CORES; REACTOR VESSELS; THERMAL HYDRAULICS
Descriptors DEC
CONTAINERS; ENERGY SOURCES; FLUID MECHANICS; FUELS; HYDRAULICS; MATERIALS; MECHANICS; NUCLEAR REACTIONS; REACTOR COMPONENTS; REACTOR MATERIALS; SIMULATION

Optional Information

Notes
(c) 2007 American Institute of Physics