학술논문

CHEMICAL ENGINEERING DIVISION, FUEL CYCLE TECHNOLOGY QUARTERLY REPORT, OCTOBER--DECEMBER 1971.
Document Type
Technical Report
Author
Source
Other Information: UNCL. Orig. Receipt Date: 31-DEC-72
Subject
N40450* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing CENTRIFUGES
CHEMICAL PREPARATION
DECLADDING
FBR TYPE REACTORS
FLUIDIZED BED
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
LIQUID METALS
OXIDATION
PLUTONIUM
PLUTONIUM NITRATES
PLUTONIUM OXIDES
PUREX PROCESS
QUANTITATIVE CHEMICAL ANALYSIS
REDUCTION
REPROCESSING
SPENT FUELS
STAINLESS STEELS
URANIUM
URANIUM DIOXIDE
URANYL NITRATES
X-RAY FLUORESCENCE ANALYSIS
ZINC PLUTONIUM NITRATES/Pu(NO$sub 3$)$sub 4$--UO$sub 2$(NO$sub 3$)$sub 2$, conversion to oxides, fluidized-bed process for
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$, preparation from nitrate solutions, fluidized-bed process for
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$, preparation from nitrate solutions, fluidized-bed process for
URANYL NITRATES/ Pu(NO$sub 3$)$sub 4$--UO$sub 2$(NO$sub 3$)$sub 2$, conversion to oxides, fluidized-bed process for
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$, analysis for plutonium and uranium, evaluation of x-ray fluorescence method for
PLUTONIUM/oxidation and reduction in Purex process
PLUTONIUM OXIDES PuO$sub 2$/ PuO$sub 2$--UO$sub 2$, analysis for plutonium and uranium, evaluation of x-ray fluorescence method for
LIQUID METAL FAST BREEDER REACTOR/fuel reprocessing for, development of methods of
PLUTONIUM/determination in plutonium dioxide--uranium dioxide fuel, evaluation of x-ray fluorescence method for
PUREX PROCESS/ centrifugal c
PLUTONIUM NITRATES/Pu(NO$sub 3$)$sub 4$--UO$sub 2$(NO$sub 3$)$sub 2$, conversion to oxides, fluidized-bed process for
Language
English