Published 1980 | Version v1
Book Metadata-only

Radioactive materials transport analysis of the sodium inpile loop

Creators

  • 1. Toshiba Corp, Kawasaki, Jpn

Description

Deposition of Zr/Nb-95, Ru-103/106 and Ce-141/144 showed a downstream effect. For Cs-137 and Co-60, higher deposition densities were measured at cooler and heater positions. The corrosion rate at the irradiation section was estimated to be 3.9*10/sup -5/ cm/year. A difference in leaching rates was observed between Co-60 and Mn-54. Radionuclides distribution patterns along the loop were analyzed. Sticking coefficients were determined. 6 refs

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
Washington, DC
Imprint Title
International conference on liquid metal technology in energy production proceedings, 2nd, 1980
Journal Page Range
p. 17.21-17.28.

Conference

Title
2. international conference of liquid metal technology for energy systems.
Dates
20 - 24 Apr 1980.
Place
Richland, WA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14729035
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
JRR-2 REACTOR; MASS TRANSFER; PRIMARY COOLANT CIRCUITS; RADIOACTIVITY; RADIOACTIVITY TRANSPORT; RADIONUCLIDE MIGRATION; SODIUM COOLED REACTORS
Descriptors DEC
COOLING SYSTEMS; ENRICHED URANIUM REACTORS; ENVIRONMENTAL TRANSPORT; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS