Design study of fusion DEMO plant at JAERI

Tobita, K.; Nishio, S.; Enoeda, Mikio; Satō, Masayasu; Isono, T.; Sakurai, S.; Nakamura, Haruto; Satô, Sennosuke; Suzuki, Satoshi; Ando, Masami; Ezato, Koichiro; Hayashi, Takao; Hirose, Takanori; Inoue, Takashi; Kawamura, Y.; Koizumi, N.; Kudo, Yusuke; Kurihara, Ryoichi; Kuroda, T.; Matsukawa, M.; Mouri, K.; Nakamura, Y.; Nishi, M.; Nomoto, Yasunobu; Ohmori, J.; Oyama, N.; Sakamoto, K.; Suzuki, Takahiro; Takechi, M.; Tanigawa, Hiroyasu; Tsuchiya, Kazuyoshi; Tsuru, Daigo

doi:10.1016/j.fusengdes.2005.08.058

Cited by 139 publications

(59 citation statements)

References 18 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The design parameters of K-DEMO used in simulations are R = 6.8 m, a = 2.1 m, I p = 12 MA, toroidal field of 7.4 T, κ = 2.0, and δ = 0.625 [23]. For Japanese DEMO, three different models are investigated; model A, model B and model C. The design parameters used in simulations can be seen in table 1 [24]. In addition to the parameter used in table 1, it is calculated that tokamak built by model C will have the most weight of 23,900 ton, while the tokamak built by model C will have the lowest weight of 15,700 tons.…”

Section: Demo Simulationsmentioning

confidence: 99%

Impurity accumulation and performance of ITER and DEMO plasmas in the presence of transport barriers

Chatthong

Promping

Onjun

2017

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

Section: Demo Simulationsmentioning

confidence: 99%

Impurity accumulation and performance of ITER and DEMO plasmas in the presence of transport barriers

Chatthong

Promping

Onjun

2017

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

“…12) (1) Demo reactor will be operated in steady or quasi-steady state. (2) Tritium will be bred in the breeding blanket.…”

Section: Operation Conditions For a Demo Reactormentioning

confidence: 99%

Operation Scenarios and Requirements for Fuel Processing in Future Fusion Reactor Facilities

O’hira

Yamanishi

Hayashi

2006

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

Operability and operation scenario of hydrogen Isotope Separation System (ISS) for ITER and a demo reactor are checked and examined based on the information in the ITER documents. It has been confirmed that the current ISS design well covers the operational requirements of the designated operation modes and other anticipated operations. However, some operation modes using rich deuterium fuel will require additional tritium inventory in the system (not only for ISS but the storage system in some cases) and make duration time between the operations longer. Operation scenario of ISS for a demo reactor will be quite simple, but the process capacity required being associated with detritiation of coolant water become excessively large without any countermeasure to control/reduce tritium permeation in the bleeding blanket operated at a temperature much higher than that of ITER.

show abstract

“…If the plasma current can be non-inductively started up, the CS could be reduced or eliminated from the Tokamak device. These provide a major technical advantage for designing a future compact reactor, such as VECTOR [1] and Slim-CS [2]. For spherical Tokamak (ST) based devices such as CTF-ST [3] and FNSF-ST [4], elimination of CS is crucial since there is a severely restricted space in the centre column of ST to hold an aspect ratio sufficiently low.…”

Section: Introductionmentioning

confidence: 99%

Non inductive formation of an extremely overdense spherical Tokamak by electron Bernstein wave heating and current drive on LATE

Uchida

Noguchi

Tanaka

et al. 2015

EPJ Web of Conferences

View full text Add to dashboard Cite

Abstract. An extremely overdense special Tokamak plasma has been non-inductively formed and maintained by electron Bernstein (EB) wave heating and current drive in the Low Aspect ratio Torus Experiment (LATE) device. The plasma current reaches 12 kA and the line-averaged electron density exceeds 7 times the plasma cut off density by injecting a 2.45 GHz microwave power of 60 kW. Such a highly overdense plasma is obtained when the upper hybrid resonance layer lies to the higher field side of the 2nd harmonic ECR layer, which may realize a good coupling to EB waves at their first propagation band. The effect of the injection polarization on the mode conversion rate to EB waves at the extremely overdense regime has been investigated and an improvement in the plasma current is observed.

show abstract

Design study of fusion DEMO plant at JAERI

Cited by 139 publications

References 18 publications

Impurity accumulation and performance of ITER and DEMO plasmas in the presence of transport barriers

Impurity accumulation and performance of ITER and DEMO plasmas in the presence of transport barriers

Operation Scenarios and Requirements for Fuel Processing in Future Fusion Reactor Facilities

Non inductive formation of an extremely overdense spherical Tokamak by electron Bernstein wave heating and current drive on LATE

Contact Info

Product

Resources

About