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).

Optional Information

Secondary number(s)
CONF-870418--.