UKAEA Journals

Showing 1 - 7 of 7 Journals Results
2005

The High Efficiency Thermal Shield (HETS) concept was proposed by ENEA for divertor application in the context of the ITER project and as part of the European Power Plant Conceptual Study. The design is modular, and the unit dimensions are of the order of centimeters for limiting mechanical and thermal stresses. This paper presents results of therm…

Published
2005

Modelling of temperature excursions in structures of conceptual power plants during hypothetical worst-case accidents has been performed within the European Power Plant Conceptual Study (PPCS). A new, 3D finite elements (FE) based tool, coupling the different calculations to the same tokamak geometry, has been extensively used to conduct the neutro…

Published
2005

A full orbit code is used to compute collisionless losses of fusion particles from three proposed burning plasma tokamaks: the International Tokamak Experimental Reactor ITER; a spherical tokamak power plant (STPP) [T. C. Hender, A. Bond, J. Edwards, P. J. Karditsas, K. G. McClements, J. Mustoe, D. V. Sherwood, G. M. Voss, and H. R. Wilson, Fusion …

Published
2005

The HERCULES code was designed and developed to assist in the safety and environmental analysis tasks of the European Power Plant Conceptual Study (PPCS). However, its capabilities extend beyond this kind of analysis: coupling of the different computational tools and nuclear databases to the same geometry and material compositions, automation of in…

Published
2005

Materials research represents a significant part of the European and world effort on fusion research. Detailed knowledge of materials properties is needed in the design by analysis of power plant and experimental machine components, and in testing to design fusion materials with specific properties, a process that involves collection and examinatio…

Published
2005

An analysis has been made of the IFMIF lithium loop activation using the time-dependent, activation, transport and deposition code, TRACT (TRansport of ACTivation). Corresponding operator dose rates have also been derived using the neutron and photon transport Monte Carlo code MCNP-4C, enabling an assessment of operator exposure, both during IFMIF …

Published
2003

As part of the European Power Plant Conceptual Study, two different divertor designs were proposed, based on previous work on HETS (High Efficiency Thermal Shield) performed at FZK and ENEA. The coolant is helium gas at pressures in the range 10-14 MPa and the inlet temperatures are in the range of 500-800 o C. The geometrical complexity of the des…

Published