Published 1999 | Version v1
Computer medium

A scaling approach for fluid mixing in rapid boron-dilution transients

  • 1. Dept. of Materials and Nuclear Engineering, Univ. of Maryland, College Park, MD (United States)

Description

The issue of rapid-boron dilution transients has been investigated for a decade with few definitive conclusions. The potential reactivity insertion that would result from the transport of a boron-dilute slug to the core region depends on the spatial and temporal concentration of neutron poison in the fluid that penetrates the core. Difficulties in assessing the consequences of a boron-dilution transient lie in the diversity of postulated on-set scenarios, and in the large dependence of the resulting reactivity insertion on plant conditions and geometric features. The University of Maryland (UM) 2 x 4 Thermohydraulic Loop Facility is collecting code validation data for rapid boron-dilution transients. The data has to be representative of the prototype. scaling thus becomes an important consideration. The mixing of the boron-dilute slug with the highly borated coolant present in the primary system is advective-diffusive. Therefore, the scaling approach involves extracting relevant parameters from the advection-diffusion equation. The dimensionless numbers that govern mixing are shown to be the Strouhal and Schmidt numbers. They have to be considered simultaneously to properly scale the flow in the model facility. A closer investigation of the relation between these two numbers reveals that, for fully developed turbulent flows, matching only one of these numbers is sufficient. This conclusion is substantiated by experimental results from Vattenfall. (author)

Part of:
ICONE-7: Proceedings of the 7th international conference on nuclear engineering

Additional details

Publishing Information

Publisher
Japan Society of Mechanical Engineers
Imprint Place
Tokyo (Japan)
Imprint Title
ICONE-7: Proceedings of the 7th international conference on nuclear engineering
Imprint Pagination
4252 p.
Journal Page Range
[12 p.]

Conference

Title
7. international conference on nuclear engineering
Acronym
ICONE-7
Dates
19-23 Apr 1999
Place
Tokyo (Japan)

Optional Information

Notes
This CD-ROM can be used for WINDOWS 95/98/NT, MACINTOSH and UNIX; Acrobat Reader 3.0.1 is included; Data in PDF format, Track No. 07, ICONE-7223