THE AQUEOUS, HOMOGENEOUS, SUSPENSION REACTOR OF THE KEMA

Journal Article · Fri Nov 01 00:00:00 EST 1963 · Atomwirtschaft (West Germany) Changed to ATW, Atomwirtsch., Atomtech.

OSTI ID:4147591

Hermans, M E.A.; Kersten, J A.H.; Went, J J

The concept of the KEMA is based on the opinion that, in the long run, only the development of a so-called breeder reactor represents an effective solution of the energy shortage which the future threatens. The breeder reactor offers the possibility of converting U/sup 238/, or Th/sup 232/ which are thermally not fissionable, into Pu/sup 239/ or U/sup 233/, respectively and so the utilization of practically unlimited supplies or low grade ores. A thermal breeder reactor which uses the Th/sup 232//U/sup 233/ cycle has a maximum conversion factor when neutron absorbing material in the reactor is avoided by the use of heavy water as moderator and a homogeneous construction. A further increase in the conversion factor can be obtained if the reactor is so constructed that the fission products can be removed either wholly or in part during reactor operation. In a homogeneous water reactor the fissionable material may be used in the form either of dissolved salts or of oxide particles. In both cases the fissionable element is easy to make and the reprocessing is simpler and cheaper. Capital investment in heavy water is relatively smaller for the reactor dealt with here than for a comparable heterogeneous type. The aim of the development work is to establish whether aqueous suspensions can be used as the fissionable material for homogeneous reactors and where the limits lie. The extent to which aqueous suspensions form serviceable fissionable materials will only be known after the completion of these experiments, called the KEMA suspension test reactor (KSTR). Before constructing the KSTR a sub-critical assembly was built to obtain the first results on the kinetic, physical, and chemical behavior of the reactor. The KSTR is to be a critical assembly in which a suspension of about 4% by volume of a UO/sub 2/-ThO/sub 2/ mixed oxide in light water is circulated in a system consisting of a reactor vessel, a heat exchanger, and a pump. The fissionable material and erosion problems are the subject of extensive research. (auth)

• Research Organization: Kernreaktorlaboratorium der KEMA, Arnhen, Ger.
• NSA Number: NSA-18-006497
• OSTI ID: 4147591
• Journal Information: Atomwirtschaft (West Germany) Changed to ATW, Atomwirtsch., Atomtech., Vol. Vol: 8; Other Information: Orig. Receipt Date: 31-DEC-64
• Country of Publication: Country unknown/Code not available
• Language: German

Related Subjects

REACTOR TECHNOLOGY
ABSORPTION
BREEDING
CAPTURE
CHEMICAL REACTIONS
CONVERSION
COOLANT LOOPS
CORROSION
CRITICAL ASSEMBLIES
DECONTAMINATION
DELAYED NEUTRONS
ECONOMICS
EFFICIENCY
EROSION
FABRICATION
FERTILE MATERIALS
FISSION PRODUCTS
FISSIONABLE MATERIALS
FLUID FLOW
FUEL SOLUTIONS
FUEL SUSPENSIONS
GRAIN SIZE
HEAT EXCHANGERS
HEAT TRANSFER
HEAVY WATER
HEAVY WATER MODERATOR
HOMOGENEOUS REACTORS
KSTR
MATERIALS TESTING
MECHANICAL STRUCTURES
NEUTRON FLUX
ORES
OXIDES
PLUTONIUM 239
PUMPS
REACTIVITY
REACTOR CORE
REACTORS
REPROCESSING
RESEARCH REACTORS
SALTS
SUSPOP
THERMAL NEUTRONS
THORIUM 232
THORIUM OXIDES
TRANSFER FUNCTIONS
URA