Results 171 to 180 of about 525,516 (210)

Aqueous tritium breeding blanket with natural lithium

Fusion Engineering and Design, 1989
An aqueous tritium breeding blanket concept with natural lithium has been proposed. Lithium oxide dissolved in pressurized heavy water forms a saturated solution of LiOD in the liquid phase and the remainder is suspended in the solution or forms a breeder solid skeleton.
Masabumi Nishikawa, Toshihiko Kawano, Kenzo Munakata, Yukinori Kanda, Hideki Nakashima   +4 more
openaire   +1 more source

Neutronics Optimization of Tritium Breeding Blanket for the FDS

Plasma Science and Technology, 2002
Neutronics optimization calculations have been performed for the tritium breeding blankets with solid ceramic breeder Li2O and liquid eutectic breeder Li17Pb83, respectively, based on a 2-D geometrical configuration using the Monte Carlo neutron-photon transport code MCNP/4B.
Zheng Shan-liang, Wu Yi-can, Huang Qun-ying   +2 more
openaire   +1 more source

An on-line method for tritium breeding studies in Li-blankets

Nuclear Instruments and Methods in Physics Research, 1982
Abstract An on-line method for tritium breeding measurements in lithium blankets is described. The apparatus comprizes two tiny ionization chambers (≈ 1.3 cm 3 each) separated by a common electrode holding 6 LiF radiating materials. Tritium producing events due to neutron interaction with the radiating material result in triton and alpha particles ...
O.P. Joneja, R. Hecker, A. Mohsin
openaire   +1 more source

Enhancing tritium breeding characteristics of a fusion reactor blanket

Annals of Nuclear Energy, 1998
Abstract In this paper we have reported our results of a detailed time dependent study of neutron spectra, tritium production rate, tritium breeding ratio, slowing down time and average energy following a pulse of 14 MeV neutrons in Li+C assemblies of different sizes. We have solved the time dependent diffusion equation with energy dependent buckling
Sanjay Gupta, Suresh Garg, Feroz Ahmed
openaire   +1 more source

Tritium breeding control within liquid metal blankets

Fusion Engineering and Design, 2013
Abstract A key requirement for DEMO is the on-site breeding of tritium. In order to do this, a robust control system must be employed to ensure enough tritium is being bred to sustain the fusion reactor, whilst not breeding an amount which would exceed the plant's tritium inventory license.
L. Morgan, J. Pasley
openaire   +1 more source

Design of a tritium breeding blanket for volumetric neutron source

Fusion Engineering and Design, 1998
Abstract A water-cooled and austenitic stainless-steel-structured breeding blanket system is designed for a volumetric neutron source (VNS), based on a steady-state tokamak device. The designed VNS with super-conducting coils has a 4.5 m main radius and a total of 300 MW in fusion power.
Y. Asaoka, Y. Ogawa, K. Okano, N. Inoue, Y. Murakami, K. Tomabechi, T. Yamamoto, T. Yoshida   +7 more
openaire   +1 more source

Evaluation of Applicability of Geant4 and OpenMC in Tritium Breeding Calculation for Fusion Blanket

Journal of Fusion Energy
Jingyu Sun, Haibing Guo, Jimin Ma
exaly   +2 more sources

Tritium management and safety issues in ITER and DEMO breeding blankets

Fusion Engineering and Design, 2013
Abstract Safe, reliable and efficient tritium management in the breeder blanket faces unique technological challenges. Beside the tritium recovery efficiency in the tritium extraction and coolant purification systems, the tritium tracking accuracy between the inner and outer fuel cycle shall also be demonstrated.
Bornschein, B., Day, Chr., Demange, D., Pinna, T.   +3 more
openaire   +3 more sources

A blanket concept with liquid Li17Pb83 for tritium breeding in INTOR-NET

Nuclear Engineering and Design. Fusion, 1984
Abstract A blanket concept with eutectic Li17Pb83 as liquid breeder, suited for tritium production in an experimental Tokamak power reactor is outlined and discussed. This design has been developed to satisfy the INTOR-Phase-I specifications, in particular: (i) modular arrangement of the blanket units inside the vacuum vessel; (ii) no use of the heat
J. Airola, M. Biggio, G. Casini, F. Farfaletti-Casali, P. Li Bassi, C. Ponti, M. Rieger, C. Piana   +7 more
openaire   +1 more source

Tritium breeding performance of a self-cooled water based blanket

Fusion Engineering and Design, 1987
Abstract A major issue in the design of fusion reactor blankets is the trade-off between tritium breeding and other blanket design requirements. While net breeding is required, the blanket design should also ensure adequate heat removal, efficient power production and sufficient shielding.
M.J. Embrechts, D. Steiner, G. Varsamis, L. Deutsch, P. Gierszewski   +4 more
openaire   +1 more source