Published 1977 | Version v1
Book

Natural circulation in FFTF, a loop type LMFBR

  • 1. Hanford Engineering Development Lab., Richland, WA

Description

The authors present a state-of-the-art review of natural circulation heat transfer in loop type reactor plants. Most of the examples are taken from Fast Flux Test Facility (FFTF) design experience, drawing on the authors' familiarity and a developing base of available documentation. On-going studies related to the Clinch River Breeder Reactor (CRBR) and some foreign experience are also noted where available in the literature. The emphasis is on the role of natural circulation in decay heat removal; however, free convection during either operation at power or normal shutdown does influence some aspects of the design and these are reviewed. In treating decay heat removal the topics discussed include steady state loop performance and transient dynamics for conditions immediately after scram and for the longer term which involves different considerations. The review summarizes complex dynamics, specific to the FFTF design evaluation, which particularly illustrate large available margins for decay heat removal (possibly involving coolant boiling). Also addressed are modelling considerations and the status of experimental programs for loop reactor applications. 28 references

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York
Imprint Title
Thermal and hydraulic aspects of nuclear reactor safety. Vol II
Journal Page Range
p. 265-283.

Conference

Title
Winter annual meeting of the American Society of Mechanical Engineers.
Dates
27 Nov - 2 Dec 1977.
Place
Atlanta, GA, USA.