Published 1988 | Version v1
Book Metadata-only

Breakup and quench of molten metal fuel in sodium

Creators

  • 1. Argonne National Lab., IL (USA). Reactor Analysis and Safety Div.

Description

This paper reports on tests in which the breakup behavior of kilogram quantities of molten uranium, uranium-zirconium alloy, and uranium-iron alloy pour streams on 600 C sodium was studied. A sodium depth of less than 0.3 m was required for hydrodynamic breakup and freezing of 25-mm pour streams of uranium and uranium-zirconium alloy with up to 400 C melt superheat. The breakup material was primarily in the form of filaments and sheets with a settled bed voidage on the order of 0.9. The uranium-iron alloy with 800 C melt superheat exhibited similar behavior except a sodium depth somewhat greater than 0.3 m was required for breakup and freezing of the particles

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
89448-1460-0
Imprint Title
Proceedings of the international topical meeting on safety of next generation power reactors
Imprint Pagination
933 p.
Journal Page Range
p. 838-843.

Conference

Title
American Nuclear Society topical meeting on the safety of next generation power reactors.
Dates
1-5 May 1988.
Place
Seattle, WA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22023561
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL-COOLANT INTERACTIONS; IRON ALLOYS; MOLTEN SALT FUELS; SODIUM; SODIUM COOLED REACTORS; SUPERHEATING; URANIUM; URANIUM ALLOYS; ZIRCONIUM ALLOYS
Descriptors DEC
ACTINIDE ALLOYS; ACTINIDES; ALKALI METALS; ALLOYS; ELEMENTS; ENERGY SOURCES; FUELS; HEATING; LIQUID FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS

Optional Information

Secondary number(s)
CONF-880506--.