/sup 244/CmO/sub 2//nat. -UO/sub 2/ hybrid blanket with flat fission power production

Conference · Fri Jan 01 04:00:00 EST 1988 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5819465

Sahin, S; Erisen, A; Cebi, Y

In the present study, /sup 244/CmO/sub 2/ is mixed with nat.-UO/sub 2/ for the purpose of power flattening in a hybrid blanket with a reasonably high energy multiplication factor. Also, the temporal variations of the fission power density (FPD) are observed during an 18-month plant operation period. The main conclusion drawn from this work is that it became possible to keep a flat fission power profile (FPP) over a very long plant operation period of 18 months by simply omitting the beryllium multiplier in the blanket and keeping the neutron spectrum fairly unchanged throughout the fission zone. This reduced the efforts for fuel management to a minimum. A further observation focused on only minor variations of the integral neutronic data over longer plant operation periods. Among others, the fission power generation increase is also very modest. This results in an optimum investment for the nonnuclear island. The blanket burns up high-level nuclear waste /sup 244/Cm effectively, with efficient electricity production and breeding of a new type of nuclear fuel /sup 245/Cm with very superior nuclear properties. Finally, a warning should be issued for the careful international safeguarding of such a hybrid plant due to the extremely high quality of the bred plutonium fuel.

• Research Organization: Gazi Univ. (Turkey)
• OSTI ID: 5819465
• Report Number(s): CONF-881011-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 57
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALKALINE EARTH METALS
ALPHA DECAY RADIOISOTOPES
BERYLLIUM
BREEDING BLANKETS
CHALCOGENIDES
CURIUM 244
CURIUM COMPOUNDS
CURIUM ISOTOPES
CURIUM OXIDES
ELEMENTS
EVEN-EVEN NUCLEI
FISSION
FUEL ELEMENTS
FUEL MANAGEMENT
FUEL RODS
FUSION YIELD
GEOMETRY
HEAVY NUCLEI
HIGH-LEVEL RADIOACTIVE WASTES
HYBRID REACTORS
IRRADIATION
ISOTOPES
KINETICS
MATERIALS
MATHEMATICS
METALS
MULTIPLICATION FACTORS
NATURAL URANIUM
NEUTRON SPECTRA
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEI
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM
POWER DENSITY
PROLIFERATION
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
SAFEGUARDS
SPECTRA
THORIUM COMPOUNDS
THORIUM OXIDES
TRANSPLUTONIUM COMPOUNDS
TRANSURANIUM COMPOUNDS
TRANSURANIUM ELEMENTS
URANIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
USES
WASTES
YEARS LIVING RADIOISOTOPES
YIELDS