Published 1976 | Version v1
Book

The highly shielded extraction facility MILLI at Kernforschungszentrum Karlsruhe (KFK)

  • 1. Kernforschungszentrum Karlsruhe (Germany, F.R.). Inst. fuer Heisse Chemie
  • 2. Kernforschungszentrum Karlsruhe (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle
  • 3. Kernforschungszentrum Karlsruhe (Germany, F.R.). Projekt Nukleare Sicherheit

Description

The miniature pilot plant MILLI was designed for experiments on dissolution and extraction of highly irradiated fast breeder fuels. The layout capacity is 1kg fuel per day and per cycle. The facility is in hot operation since 1971 and enables experiments to be performed with highly active material and every plutonium concentration. One dissolver and filter, the first ''co-decontamination'' and the second partitioning cycle are located in two hot cells. The heavy concrete shielding of these cells allows the handling of 300,000-Ci γ-radioactive material with 1-MeV energy in each. The third extraction cycle is contained in a gas-tight glove-box. A description is given of the cells and auxiliary equipment. The extractors used are flat mixer-settlers, critically safe by geometry. The containers are 40-to 50-mm- thick slab-tanks or sandwich tanks. Over a period of five years different experiments with highly active materials have been achieved in MILLI. (author)

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna
ISBN
92-0-020476-7
Imprint Title
Design of and equipment for hot laboratories
Series
Proceedings series.
Journal Page Range
p. 87-93.

Conference

Title
Symposium on the design of and equipment for hot laboratories.
Dates
2 - 6 Aug 1976.
Place
Otaniemi, Finland.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
9360695
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
GLOVEBOXES; HOT CELLS; HOT LABS; LABORATORY EQUIPMENT; MIXER-SETTLERS; RADIATION PROTECTION; RADIOACTIVE WASTE PROCESSING; REPROCESSING; SPENT FUELS
Descriptors DEC
ENERGY SOURCES; EXTRACTION APPARATUSES; FUELS; MANAGEMENT; NUCLEAR FUELS; REACTOR MATERIALS; SEPARATION PROCESSES; WASTE MANAGEMENT; WASTE PROCESSING

Optional Information

Secondary number(s)
IAEA-SM--209/25.