Published November 1975 | Version v1
Journal article Metadata-only

Process technology for the MSR 233U--Th cycle

Creators

  • 1. Oak Ridge National Lab., TN

Description

After a brief description of the design features of the molten-salt breeder reactor, fuel processing for removal of $sup 233$Pa and fission products is examined. Some recent developments in processing technology are discussed. (JWR)

Additional details

Identifiers

DOI
10.2172/4129264;

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
22
Series
Trans. Am. Nucl. Soc.
Journal Page Range
338-339

Conference

Title
American Nuclear Society 1975 winter meeting.
Dates
16 Nov 1975.
Place
San Francisco, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7252457
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
BREEDER REACTORS; FUEL CYCLE; MOLTEN SALT FUELS; MOLTEN SALT REACTORS; REPROCESSING; THORIUM; URANIUM 233
Descriptors DEC
ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; FUELS; HEAVY NUCLEI; ISOTOPES; LIQUID FUELS; METALS; NUCLEAR FUELS; NUCLEI; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
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