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Sagayama, Yutaka; Ando, Masato
Nihon Genshiryoku Gakkai-Shi ATOMO, 60(3), p.162 - 167, 2018/03
The Generation IV international Forum (GIF) has led international collaborative efforts to develop six next generation nuclear energy systems, such as Sodium-cooled Fast Reactor (SFR), Lead-cooled Fast Reactor (LFR), Gas-cooled Fast Reactor (GFR), Molten Salt Reactor (MSR), Supercritical Water-cooled Reactor (SCWR), and Very High Temperature Reactor (VHTR), which have superior characteristics for the Safety and Reliability, Economics, Sustainability, Proliferation Resistance and Physical Protection. Some systems are already in the Demonstration Phase and the commercialization of the system in 2030s, which is the target of GIF, comes into sight.
Oki, Shigeo
JNC TN9400 2000-007, 77 Pages, 1999/12
Comparative study for various core concepts is being carried out in a frame work of the study for minor actinide (MA) transmutation using a fast reactor. Different fuel types (Oxide, Nitride, Metal) and coolants (Sodium, Lead) were investigated. It is found that neither nitride nor metal-fueled core has significantly more excellent efficiency for MA transmutation comparing with an oxide-fueled core when the basic performance of these cores as a power reactor are fixed. The MA transmutation Properties of lead-cooled fast reaetor (BREST-300) and sodium-cooled fast reactor (3800MWth large core) were compared. The sodium-cooled reactor surpasses BREST-300 on the MA transmutation rate. Meanwhile, it is found that BREST-300 is excellent from the viewpoint of loading much more MA in the core to attain larger MA transmutation amount. The effect of MA to coolant void reactivity is considered by the sensitivity analysis. It is found that the lead void reactivity has different sensible energy regions on MA nuclides from those for the sodium void reactivity.
Mukaiyama, Takehiko; Ogawa, Toru;
IAEA-TECDOC-783, 0, p.105 - 114, 1995/01
no abstracts in English