Published 1983 | Version v1
Book

Uranium enrichment by the separation nozzle process

  • 1. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Kernverfahrenstechnik

Description

The separation nozzle process developed by the Karlsruhe Nuclear Research Centre is based on the centrifugal force in a curved jet consisting of uranium hexafluoride and a light auxiliary gas. It is applied on a technical scale in Brazil, where a cascade section consisting of 24 separation stages is being constructed which will be extended in two steps into a demonstration plant with a capacity of roughly 300,000 SWU/a. To produce separation nozzle systems with extremely small characteristic dimensions permitting plant operation at atmospheric pressure, a manufacturing process is being developed which relies on combined X-ray lithography and microgalvanic deposition (LIGA process). By applying this technology the prototype separation stages under construction at the Karlsruhe Nuclear Research Centre should lead to commercial separation nozzle plants with capacities between one and four million SWU/a. Less than 300 separation stages are required for cascades with a product assay of 3.2% and a tails assay of 0.25% 235U. A cost evaluation is given for such plants. (author)

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna
ISBN
92-0-050283-0
Imprint Title
Nuclear power experience
Imprint Pagination
893 p.
Series
Proceedings series.
Journal Page Range
v. 3 p. 513-525.

Conference

Title
International conference on nuclear power experience.
Dates
13-17 Sep 1982.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
14779647
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COST; ECONOMICS; ISOTOPE SEPARATION; ISOTOPE SEPARATION PLANTS; LICENSING; NOZZLES; PILOT PLANTS; SAFEGUARDS; SEPARATION NOZZLE METHOD; SPECIFICATIONS; URANIUM
Descriptors DEC
ACTINIDES; ELEMENTS; FUNCTIONAL MODELS; INDUSTRIAL PLANTS; METALS; NUCLEAR FACILITIES; SEPARATION PROCESSES

Optional Information

Secondary number(s)
IAEA-CN--42/382.