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Development of partitioning method. Recovery and utilization of useful elements in spent fuel (literature survey)

Abstract

Spent fuels from nuclear power stations contain many useful elements, which can be utilized as heat and irradiation sources, radioisotope, elemental resource, etc. Their recovery from spent fuel and effective uses have the advantages in not only converting the radioactive waste to beneficial resources but also promoting rationalization of the management and disposal of the radioactive wastes. In present study, published literature related to recovery and utilization of useful elements in spent fuel was mainly surveyed, present states and trends in their research and development were analyzed, and their future prospects were conjectured. Research and development on recovery and utilization of useful elements are being continued mainly in USA, Europe and Japan. A transportable food irradiator with Cs-137 and an electric power source with Sr-90 for remote weather station are typical examples in major past applications. However, research and development on recovery and utilization are not so much active and the future efforts should be expected hereafter. Present study was conducted under the auspices of the Science and Technology Agency of Japan. (author).
Authors:
Kondo, Yasuo; Kubota, Masumitsu; [1]  Abe, Tadashi; Nagato, Kotaro
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Sep 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-147
Reference Number:
SCA: 052001; 050800; PA: JPN-91:012196; SN: 92000659230
Resource Relation:
Other Information: PBD: Sep 1991
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; RADIOACTIVE WASTE PROCESSING; FISSION PRODUCTS; USES; RADIATION SOURCES; IRRADIATION DEVICES; REVIEWS; SEPARATION PROCESSES; RADIOACTIVE WASTES; SPENT FUELS; TRANSURANIUM ELEMENTS; RARE EARTHS; TECHNETIUM 99; PLATINUM METALS; CESIUM 137; STRONTIUM 90; PARTITION; 052001; 050800; WASTE PROCESSING; SPENT FUELS REPROCESSING
OSTI ID:
10117103
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92768118; TRN: JP9112196
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
200 p.
Announcement Date:
Jun 30, 2005

Citation Formats

Kondo, Yasuo, Kubota, Masumitsu, Abe, Tadashi, and Nagato, Kotaro. Development of partitioning method. Recovery and utilization of useful elements in spent fuel (literature survey). Japan: N. p., 1991. Web.
Kondo, Yasuo, Kubota, Masumitsu, Abe, Tadashi, & Nagato, Kotaro. Development of partitioning method. Recovery and utilization of useful elements in spent fuel (literature survey). Japan.
Kondo, Yasuo, Kubota, Masumitsu, Abe, Tadashi, and Nagato, Kotaro. 1991. "Development of partitioning method. Recovery and utilization of useful elements in spent fuel (literature survey)." Japan.
@misc{etde_10117103,
title = {Development of partitioning method. Recovery and utilization of useful elements in spent fuel (literature survey)}
author = {Kondo, Yasuo, Kubota, Masumitsu, Abe, Tadashi, and Nagato, Kotaro}
abstractNote = {Spent fuels from nuclear power stations contain many useful elements, which can be utilized as heat and irradiation sources, radioisotope, elemental resource, etc. Their recovery from spent fuel and effective uses have the advantages in not only converting the radioactive waste to beneficial resources but also promoting rationalization of the management and disposal of the radioactive wastes. In present study, published literature related to recovery and utilization of useful elements in spent fuel was mainly surveyed, present states and trends in their research and development were analyzed, and their future prospects were conjectured. Research and development on recovery and utilization of useful elements are being continued mainly in USA, Europe and Japan. A transportable food irradiator with Cs-137 and an electric power source with Sr-90 for remote weather station are typical examples in major past applications. However, research and development on recovery and utilization are not so much active and the future efforts should be expected hereafter. Present study was conducted under the auspices of the Science and Technology Agency of Japan. (author).}
place = {Japan}
year = {1991}
month = {Sep}
}