منابع مشابه
Advanced Fast Reactor:
The AFR concept is being developed at Argonne National Laboratory, as an extension of earlier work done on the Integral Fast Reactor (IFR). That work was undertaken specifically to resolve some pressing technical issues in safety, waste management, nonproliferation, and economics. Also important, however, was the fundamental fact that the efficient utilization of uranium resources is crucial to...
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We give bounds on Kazhdan constants of abelian extensions of (finite) groups. As a corollary, we improved known results of Kazhdan constants for some meta-abelian groups and for the relatively free group in the variety of p-groups of lower p-series of class 2. Furthermore, we calculate Kazhdan constants of the tame automorphism groups of the free nilpotent groups.
متن کاملFast Reactor Physics and Computational Methods
Six advanced reactor concepts have been selected for Generation-IV reactors and are being investigated worldwide to meet the challenging goals of effective resource utilization and waste minimization (sustainability), improved safety, enhanced proliferation resistance, and reduced system cost. [1] The six systems are very high temperature reactor (VHTR), sodium-cooled fast reactor (SFR), superc...
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The limited indigenous uranium resource coupled with the need of energy independence necessitated the Department of Atomic Energy (DAE) in India to opt for a three-stage nuclear power program comprising of PHWRs in Stage 1, FBRs in Stage 2 and Th-U based reactors in Stage 3, respectively to meet the energy needs of the growing Indian economy. Presently the country has stepped into the 2nd Stage...
متن کاملThe Sodium-cooled Fast Reactor (sfr)
The Sodium-cooled fast reactor (SFR) features a closed fuel cycle for efficient conversion of fertile uranium and management of minor actinides. A full actinide-recycle fuel cycle is envisioned with two major options: One involves intermediatesized (150 to 500 MWe) sodium-cooled fast reactors with uranium-plutonium-minor-actinidezirconium metal alloy fuel, supported by a fuel cycle based on pyr...
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ژورنال
عنوان ژورنال: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
سال: 1970
ISSN: 0004-7120
DOI: 10.3327/jaesj.12.453