UKAEA Journals

Showing 1 - 10 of 14 Journals Results
2020
UKAEA-CCFE-PR(20)140

Finite element analysis (FEA) is widely used in engineering to accurately model physical systems. FEA enables multi-physics investigations to be undertaken efficiently and increases the cohesiveness of interdisciplinary engineering assessments. Thanks to the recent implementation of the FEA Unstructured Mesh capability (UM) into MCNP6, radiation tr…

Preprint Purchase
The published version of this paper is currently under embargo and will be available on 02/02/2023
2015
CCFE-PR(15)28

Shutdown dose rate calculations have been performed on an integrated ITER C-lite neutronics model with equatorial port 10. A fully shielded configuration, optimized for a given diagnostic designs (i.e. shielding in all available space within the port plug drawers), results in a shutdown dose rate in the port interspace, from the activation of mater…

Preprint Published
2014

The In-Vessel Viewing System (IVVS) units proposed for ITER are deployed to perform in-vessel examination. During plasma operations, the IVVS is located beyond the vacuum vessel, with shielding blocks envisaged to protect components from neutron damage and reduce shutdown dose rate (SDR) levels. Analyses were conducted to determine the effectivenes…

Published
2013

This work presents new integral data measured at the ASP 14 MeV neutron irradiation facility at Aldermaston in the UK, which has recently become available for fusion-related work through the CCFE materials programme. Measurements of reaction products from activation experiments using elemental foils were carried out using gamma spectrometry in a hi…

Published
2013

The In-Vessel Viewing System (IVVS) in ITER consists of six identical units which are deployed between pulses or during shutdown, to perform visual examination and metrology of plasma facing components. The system is housed in dedicated ports at B1 level, with deployment at the level between the divertor cassettes and the lowermost outboard blanket…

Published
2012

The scope, methodology, and preliminary results are presented of a series of neutron transport and activation analyses aimed at updating the ITER radioactive inventory assessment and assisting the waste management planning. Calculations are performed using stateof-the-art three-dimensional models, codes, and data libraries and thereby overcoming ea…

Published
2011

In support of the technological requirements for fusion, the UK fusion technology programme is conducting several experiments using the ASP DT neutron irradiation facility at AWE Aldermaston. The present experimental programme covers two key areas of technology development: improving the quality of nuclear cross-section data required for fusion-rel…

Published
2009

Systematic analysis of the radiation fields throughout the ITER core LIDAR diagnostic system were performed to support the design optimisation and assessment process, aiming at achieving the required performance in terms of reliability, occupational safety and interface with neighboring systems. Neutron, photon, nuclear heat and material activation…

Published
2009

Within the framework of the International Energy Agency, an international collaborative study on fusion radioactive waste has been initiated to examine the back end of the materials cycle as an important stage in maximizing the environmental benefits of fusion as an energy provider. The study addresses the management procedures for radioactive mate…

Published
2006

Lithium-lead is a candidate tritium-generating material in conceptual designs of magnetic fusion power plants. Its prolonged utilization, ultimately during the entire lifetime of such a facility, has the potential to minimize amounts of active waste and improve the economic performance. Limits to a prolonged use are production of long-lived radioac…

Published