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Material control and accountability aspects of safeguards for the USA /sup 233/U/TH fuel recycle plant

Technical Report ·
DOI:https://doi.org/10.2172/6441129· OSTI ID:6441129
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Two fuel cycles are considered. The highly enriched uranium (HEU) cycle uses uranium enriched 93% in /sup 235/U as the initial fuel. The medium enriched uranium (MEU) cycle uses uranium with a /sup 235/U enrichment less than 20% as its initial fuel. In both, /sup 233/U is bred from thorium. The HEU /sup 235/U and the /sup 233/U of both cycles are recycled. The MEU /sup 235/U is retired to waste after one reactor cycle. Typical heavy metal contents of spent fuel elements from both cycles are presented. The main functional areas of the recycle plant are Shipping, Receiving, and Storage; Reprocessing; Refabrication; and Waste Treatment. A real-time materials accountability system will manage the data provided by measurements from all four areas. Simulations of material flow used in the HTGR development program are forerunners of such a system. The material control and accountability aspects of Reprocessing and Refabrication only are discussed. The proposed accountability areas are identified and the measurement techniques appropriate to various streams crossing the boundaries of the areas are identified. Special emphasis is placed on novel nondestructive methods developed for assaying solid materials containing /sup 233/U-Th. The material form, total uranium and plutonium, and activity of selected reprocessing streams are listed. The isotopics and activity of the uranium input into Refabrication are also presented.

Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
6441129
Report Number(s):
ORNL/TM-6645
Country of Publication:
United States
Language:
English

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Related Subjects

050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
055001* -- Nuclear Fuels-- Safeguards
Inspection
& Accountability-- Technical Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACCOUNTING
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
EVEN-ODD NUCLEI
FUEL CYCLE
FUEL CYCLE CENTERS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAVY NUCLEI
HTGR TYPE REACTORS
ISOTOPES
MANAGEMENT
NUCLEAR FACILITIES
NUCLEAR MATERIALS MANAGEMENT
NUCLEI
RADIOISOTOPES
REACTORS
SAFEGUARDS
THORIUM CYCLE
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES