Subchannel thermal-hydraulic modeling of an APT tungsten target rod bundle

Technical Report · Mon Sep 01 04:00:00 EDT 1997

DOI:https://doi.org/10.2172/578631· OSTI ID:578631

Hamm, L L; Shadday, Jr, M A

The planned target for the Accelerator Production of Tritium (APT) neutron source consists of an array of tungsten rod bundles through which D{sub 2}O coolant flows axially. Here, a scoping analysis of flow through an APT target rod bundle was conducted to demonstrate that lateral cross-flows are important, and therefore subchannel modeling is necessary to accurately predict thermal-hydraulic behavior under boiling conditions. A local reactor assembly code, FLOWTRAN, was modified to model axial flow along the rod bundle as flow through three concentric heated annular passages.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-96SR18500
• OSTI ID: 578631
• Report Number(s): WSRC-MS--97-0373; CONF-970824--; ON: DE97053906
• Country of Publication: United States
• Language: English

Related Subjects

43 PARTICLE ACCELERATORS
ANNULAR SPACE
COMPUTERIZED SIMULATION
COOLANTS
COOLING SYSTEMS
HEAT TRANSFER
HEAVY WATER
HYDRAULICS
ISOTOPE PRODUCTION
NEUTRON SOURCES
SAFETY ANALYSIS
TARGET CHAMBERS
THEORETICAL DATA
TRITIUM