Results 191 to 200 of about 3,747 (225)

Helical Geometry Effect on Tritium Breeding in Heliotron Fusion Reactor Blanket

Nuclear Science and Engineering, 1984
An examination is made of the helical geometry effect on the tritium breeding in the Heliotron reactor blanket. Calculations are performed with the threedimensional Monte Carlo code MORSE-I for the cylindrical, torus and helical geometry models, each approximating the configuration of the Heliotron reactor in various degrees.
H. Hasegawa, H. Nakashima, T. Matsui, M. Ohta   +3 more
openaire   +1 more source

Tritium transport finite element modeling tools for breeding blanket design

2009 23rd IEEE/NPSS Symposium on Fusion Engineering, 2009
Permeation is a complex phenomenon. Today the unique tool ITER QA pedigree qualified is a one dimensional tool, TMAP7, not suitable for the complex geometries present in the Breeding Blanket concepts, where 2D/3D simulation capacities of the permeation phenomenon are a real need. In pursuit of this objective, a group of new operators describing some of
S. Terron, C. Moreno, L.A. Sedano, F. Gabriel, A. Abanades   +4 more
openaire   +1 more source

Tritium release behavior from liquid tritium breeding materials for fusion reactor blanket under neutron irradiation

Progress in Nuclear Energy, 1998
Abstract In-situ tritium release experiments on Li17-Pb83 molten alloy and LiF-BeF 2 molten salt were carried out using the fast neutron source reactor “YAYOI” of the University of Tokyo. Regarding Li17-Pb83, chemical form of released tritium was mainly HT or T 2 .
Takayuki Terai, Satoru Tanaka
openaire   +1 more source

Effect of Blanket Structure on Tritium Breeding Ratio in Fusion Reactors

Nuclear Technology - Fusion, 1983
Effects of blanket composition, including materials and their thicknesses, on the tritium breeding ratio in tokamak fusion reactors are investigated for the Li/sub 2/O blanket having a separable first wall. The sensitivities of the breeding ratio to the thicknesses of the materials for the first wall are estimated as follows (unit: T /SUB BR/ /cm): S ...
Koichi Maki, Takashi Okazaki
openaire   +1 more source

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

Electronic Measurement of Tritium Breeding in a Fusion Blanket Assembly

Fusion Technology, 1989
The tritium production rate (TPR) distribution in a fusion blanket assembly previously determined from measurements of tritium beta activity was remeasured using an independent electronic method. The results agreed within the experimental errors and confirmed the previously reported discrepancies with predictions based on three-dimensional Monte Carlo ...
openaire   +1 more source

Helium-3 blankets for tritium breeding in near-term fusion devices

Fusion Engineering and Design, 1989
The purpose of this paper is to propose a novel blanket concept for in-situ tritium breeding in a near-term device such as ITER. In this concept terrestial supplies of helium-3, rather than lithium, are used for tritium breeding. In order to assess the key characteristics of this concept, a reference configuration was adopted based on minor ...
D. Steiner, M.J. Embrechts, G. Varsamis, R. Vesey, P. Gierszewski, C.P.C. Wong   +5 more
openaire   +1 more source

Lithium resonance self-shielding: Effect on tritium breeding in fusion blankets

Radiation Effects, 1986
Abstract Effective cross-sections of lithium in the 250 KeV resonance range have been evaluated by different methods. Some discrepancies have been found out, indicating the need of taking into account the overlapping between the Li-6 and Li-7 resonances in order to obtain accurate tritium breeding rates.
Guillermo Velarde, Jose M. Aragones, Jose J. Honrubia, Jose M. Martinez-Val, Emilio Minguez, Jose M. Perlado, Jose M. Santolaya   +6 more
openaire   +1 more source

Aqueous Slurries as Tritium Breeding Blankets for D-T Fusion Reactors

Nuclear Technology - Fusion, 1983
Fusion reactor blankets based on an aqueous slurry concept are proposed and examined. Attractive features and disadvantages of aqueous slurries as blankets are reviewed. Calculations to determine the capacity of slurry particles with different diameters to stop recoiling tritons are described.
Theodore A. Parish, Roger D. Erwin, Michael J. Schuller   +2 more
openaire   +1 more source

Thermal-hydraulic and thermo-structural analyses of the STARFIRE/DEMO tritium-breeding blanket

Nuclear Engineering and Design. Fusion, 1984
Abstract Design features and thermal-hydraulic and thermo-structural aspects of the STARFIRE/DEMO tritium-breeding blankets are described and discussed. Design calculations which take into account thermal, mechanical, and materials performance, indicate favorable results for the viability of the blanket designs in general and point to key issues ...
Y LIU, S MAJUMDAR, B MISRA, R BURK, G MORGAN   +4 more
openaire   +1 more source