Ex-Core CFD Analysis Results for the Prometheus Gas Reactor
Creators
- 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
- DOI
- 10.1063/1.2437493;
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