Neutron shielding and blanket neutronics design

Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.952 - 954, 2004/11

https://doi.org/10.1585/jspf.80.952

Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.

Consideration for the safety of a fusion power plant

Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 78(11), p.1157 - 1164, 2002/11

https://doi.org/10.1585/jspf.78.1157

Based on the fundamental approach for safety of ITER, possible extension to assure safety of fusion power plant was considered. Although the entire analysis and licensing preparation are specific for ITER, its methodology that take full advantage of inherent feature of fusion is expected to be applied to fundamental logic of fusion power plant. Both energy and radioactive source terms that could be potential hazards are typically of order of days of operation rather than a year in the case of fission. Major difference from the test reactor ITER identified was power blanket, coolant loop and generator train that will hold high temperature and considerable amount of tritium. It is anticipated that tritium inventory and most of the tritium safety plant would essentially be same as ITER, tritium recovery and removal from blanket loop will dominate the fusion power plant tritium systems. Such a tritium system will actively remove tritium at the daily throughput comparable with the order of plant inventory. This feature suggest no dedicated off-normal systems are needed to assure safety of fusion plant from the aspect of environmental tritium release.

None

JNC TN1400 2001-014, 437 Pages, 2001/10

JNC-TN1400-2001-014.pdf:23.1MB

no abstracts in English

Forced convective heat transfer in square-ribbed coolant channels with helium gas for fusion power reactors

Takase, Kazuyuki

Fusion Engineering and Design, 49-50, p.349 - 354, 2000/11

https://doi.org/10.1016/S0920-3796(00)00395-1

no abstracts in English

lnvestigation of small and modular-sized fast reactor

; Kawasaki, Nobuchika; ; *; ; ;

JNC TN9400 2000-063, 221 Pages, 2000/06

JNC-TN9400-2000-063.pdf:8.68MB

ln this paper, feasibility of the multipurpose small fast reactor, which could be used for requirements concemed with various utilization of electricity and energy and flexibility of power supply site, is discussed on the basis of examination of literatures of various small reactors. And also, a possibility of economic improvement by learning effect of fabrication cost is discussed for the modular-sized reactor which is expected to be a base load power supply system with lower initial investment. (1) Multipurpose small reactor (a) The small reactor with 10MWe150MWe has a potential as a power source for large co-generation, a large island, a middle city, desalination and marine use. (b) Highly passive mechanism, long fuel exchange interval, and minimized maintenance activities are required for the multipurpose small reactor design. The reactor has a high potential for the long fuel exchange interval, since it is relatively easy for FR to obtain a long life core. (c) Current designs of small FRs in Japan and USA (NERI Project) are reviewed to obtain design requirements for the multipurpose small reactor. (2) Modular-sized reactor (a) ln order that modular-sized reactor could be competitive to 3200MWe twin plant (two large monolithic reactor) with 200k/kWe, the target capital cost of FOAK is estimated to be 260k/kWe for 800MWe modular, 280k/kWe for 400MWe modular and 290k/kWe for 200MWe by taking account of the learning effect. (b)As the result of the review on the current designs of modular-sized FRs in Japan and USA (S-PRISM) from the viewpoint of economic improvement, since it only be necessary to make further effort for the target capital cost of FOAK, since the modular-sized FRs requires a large amount of material for shielding, vessels and heat exchangers essentially.

Study on fusion energy conformity with global environmental Issues

Kurihara, Kenichi

Purazuma, Kaku Yugo Gakkai-Shi, 74(7), p.675 - 684, 1998/07

https://ci.nii.ac.jp/naid/110003826254

no abstracts in English

Study on fusion energy conformity with global environmental problems

Kurihara, Kenichi

Purazuma, Kaku Yugo Gakkai "Kaku Yugo Doryokuro Jitsuyoka Gijutsu Ni Kansuru Chosa", p.43 - 60, 1998/02

no abstracts in English

A Fusion power reactor concept using SiC/SiC composites

Ueda, Shuzo; Nishio, Satoshi; Seki, Yasushi; Kurihara, Ryoichi; Adachi, Junichi*; Yamazaki, Seiichiro*; DREAM-Design-Team

Journal of Nuclear Materials, 258-263, p.1589 - 1593, 1998/00

https://doi.org/10.1016/S0022-3115(98)00294-3

no abstracts in English

A Cost-effective probabilistic model to select the dominant factors affecting the variation of the component failure rate

C.Kirchsteiger*

JAERI-M 92-186, 21 Pages, 1992/11

JAERI-M-92-186.pdf:0.67MB

no abstracts in English

None

; ; ; ; ; ;

PNC TN8450 92-008, 639 Pages, 1992/06

PNC-TN8450-92-008.pdf:74.81MB

None