Published 1987
| Version v1
Book
A study of flow mixing in a PWR vessel in asymmetric cooldown faults using the FLOW3D code
- 1. UKAEA Harwell Lab. (UK). Thermal Hydraulics Div.
- 2. Central Electricity Generating Board, Barnwood (United Kingdom). Generation Development and Construction Div.
Description
The Harwell computational fluid dynamics code, FLOW3D has been used to simulate a flow mixing test in the Oconee-1 reactor. The object was to test the ability of FLOW3D to describe thermal mixing in a PWR pressure vessel for the conditions of an over-cooling fault. The code produced reasonable estimates of the thermal diffusion observed in the Oconee test, with a tendency to underpredict mixing. However, the test exhibited gross swirl and asymmetric mixing which was not predicted by FLOW3D. Sensitivity studies to investigate the effects of downcomer ovality, inlet flow vorticity and flow imbalance between loops, have not revealed the source of the observed asymmetries
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-136-3
- Imprint Title
- Anticipated and abnormal transients in nuclear power plants
- Imprint Pagination
- vp.
- Journal Page Range
- p. V-47-V-55.
Conference
- Title
- Topical meeting on anticipated and abnormal transients in nuclear power plants.
- Dates
- 12-15 Apr 1987.
- Place
- Atlanta, GA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22077672
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ASYMMETRY; COMPUTER CODES; COOLANT LOOPS; COOLING; DYNAMICS; FLUIDS; MIXING; OCONEE-1 REACTOR; PRESSURE VESSELS; PWR TYPE REACTORS; SENSITIVITY; SIMULATION; TEMPERATURE GRADIENTS; TESTING; THERMAL DIFFUSION; VORTICES
- Descriptors DEC
- CONTAINERS; DIFFUSION; ENRICHED URANIUM REACTORS; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-870418--.