JOPSS - Search Results

This study was based on a 'pancake' type fast reactor core design of 600 MW(e), which had been optimized for Pu burning with a feed Pu vector appropriate to once-through irradiation of MOX fuel in a PWR. The purpose of the study was to investigate the effects of varying the Pu vector, examining various methods of offsetting the effects of such a change, and finally to produce fuel cycles optimized for the different qualities of Pu vector within the same basic design. In addition to the reference (once-through) Pu vector, two extreme Pu vectors were examined: high quality Pu from military stockpiles; low quality Pu corresponding to the equilibrium point of multiple recycling in a Pu burning fast reactor. Variations in Pu quality were overcome by changing the fuel inventory - replacing some of the fuel by diluent material, and altering the fuel pin size. Using absorber material ( $^{10}$ B $_{4}$ C) as diluent improves the rod worth shutdown margin but degrades the Na void and Doppler safety parameters, a non-absorber diluent has the opposite effects, so a mix of the 2 material types was used to optimize the core characteristics. Of the non-absorber diluent materials examined, ZrH gave significantly better performance than all others; $^{11}$ B $_{4}$ C was the second choice for non-absorber diluent, because of its compatibility with $^{10}$ B $_{4}$ C absorber. It was not possible to accommodate the lower quality (multi-recycled) Pu vector without a significant increase in the fuel pin volume. It was not generally possible, especially with the increased fuel pin size, to achieve positive rod worth shutdown margins - this was overcome by increasing the number of control rods. For the higher quality Pu vectors to maintain ratings within limits, it was necessary to adopt hollow fuel pellets, or else to use the diluent material as an inert matrix in the fuel pellets. It proved possible to accommodate both extremes of Pu vector within a single basic design, maintaining ...

Journal Articles

Numerical simulation of buoyancy driven exchange flow in a partitioned container

; ; ; Fumizawa, Motoo

5th Triennial Int. Symp. on Fluid Control,Measurement and Visualization, 2, p.887 - 892, 1997/00

no abstracts in English

Journal Articles

Thermal-hydraulic characteristics in a tokamak vacuum vessel of fusion reactor after transient events occurred

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 3, p.1321 - 1327, 1997/00

no abstracts in English

Journal Articles

Exchange flow characteristics in a tokamak vacuum vessel of fusion reactor under the loss-of-vacuum conditions

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi

Journal of Fusion Energy, 16(1-2), p.189 - 194, 1997/00

no abstracts in English

Journal Articles

Experimental study on buoyancy-driven exchange flows through breaches of a tokamak vacuum vessel of a fusion reactor under the loss-of-vacuum-event condition

Takase, Kazuyuki; Kunugi, Tomoaki; Ogawa, Masuro; Seki, Yasushi

Nuclear Science and Engineering, 125(2), p.223 - 231, 1997/00

https://doi.org/10.13182/NSE97-A24269

Times Cited Count：11 Percentile：64.82(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects of breach area and length to exchange flow rates under the LOVA condition in a fusion reactor

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi

Fusion Technology, 30(3(PT.2B)), p.1459 - 1464, 1996/12

no abstracts in English

Journal Articles

Experimental study of buoyancy-driven exchange flow from breaches under LOVA condition

Takase, Kazuyuki; Kunugi, Tomoaki; Ogawa, Masuro; Seki, Yasushi

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.317 - 320, 1996/00

no abstracts in English

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A study on decomposition of dioxins analogues by IR laser irradiation

Development of wet process with substitution reaction for the mass production of Li $_{2}$ TiO $_{3}$ pebbles

Environmental cycle type material of CMC-Na preared by crosslinking at paste-like conditions

Numerical analysis on thermal-hydraulic and dust transport behavior in fusion reactors at loss-of-vacuum events

Hydrogel of biodegradable cellulose derivatives, 1; Radiation-induced crosslinking of CMC

A Spectroscopic comparison of samarium-doped LiYF $_{4}$ and KY $_{3}$ F $_{10}$

Thermal hydraulic characteristics during ingress of coolant and loss of vacuum events in fusion reactors

Radiation processing of biodegradable polymer, 2; Hydrogel from cellulose derivatives

Analysis on air ingress behavior in a fusion reactor under a loss-of-vacuum event

Development and application of PIE apparatuses for high-burnup LWR fuels

Preliminary numerical analysis on dust transport in fusion reactors during the loss-of-vacuum accident

Kinetic investigation of the reaction of pertechnetate with thiourea derivatives

Buoyancy-driven exchange flow through double openings with having multi flow patterns

Pu Vector Sensitivity Study for a Pu Burning Fast Reactor Part II:Rod Worth Assessment and Design Optimization

Numerical simulation of buoyancy driven exchange flow in a partitioned container

Thermal-hydraulic characteristics in a tokamak vacuum vessel of fusion reactor after transient events occurred

Exchange flow characteristics in a tokamak vacuum vessel of fusion reactor under the loss-of-vacuum conditions

Experimental study on buoyancy-driven exchange flows through breaches of a tokamak vacuum vessel of a fusion reactor under the loss-of-vacuum-event condition

Effects of breach area and length to exchange flow rates under the LOVA condition in a fusion reactor

Experimental study of buoyancy-driven exchange flow from breaches under LOVA condition