Published 1986 | Version v1
Journal article Metadata-only

Thermal conductivity of a bed of sheared, irradiated FFTF fuel

Creators

  • 1. Oak Ridge National Lab., TN (USA)

Description

Sheared or broken fuel elements are routinely handled in fuel reprocessing and could be encountered occasionally in any fuel handling operation. The internal heat generated in beds of sheared or broken fuel as a result of decay may be important in certain cases and is usually calculated from correlations derived from tests using simulated beds of fuel. This paper reports experiments in which the thermal conductivities of sheared beds of irradiated fuel were determined from temperature profiles and then compared with those calculated by using a model

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
52
Series
Trans. Am. Nucl. Soc.
Journal Page Range
46-47
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society annual meeting.
Dates
15-20 Jun 1986.
Place
Reno, NV (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19084680
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; FFTF REACTOR; FUEL ELEMENTS; HEAT TRANSFER; IRRADIATION; REPROCESSING; THERMAL CONDUCTIVITY
Descriptors DEC
ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; THERMODYNAMIC PROPERTIES

Optional Information

Secondary number(s)
CONF-860610--Summs.