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CCFE-PR(16)522016
Helium is produced in the structural materials of nuclear power plants by the nuclear transmutation following neutron irradiation. Since the solubility of helium in all the metals is extremely low, helium tends to be trapped at defects such as vacancies, dislocations and grain boundaries, which cause materials embrittlement. Density functional the…
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CCFE-PR(16)262016
Pathways-reduced analysis is one of the techniques used by the Fispact-II nuclear activation and transmutation software to study the sensitivity of the computed inventories to uncertainties in reaction cross-sections. Although deciding which pathways are most important is very helpful in for example determining which nuclear data would benefit from…
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CCFE-PR(16)592016
The detachment of a beryllium tile from the ITER Normal Heat Flux (NHF) First Wall (FW) panels would result in an unacceptable degradation of panel performance. Such detachment has previously been observed under High Heat flux (HHF) testing of NHF FW prototypes, with initiation of de-bonding at tile edges and subsequent delamination occurring betwe…
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CCFE-PR(16)532016
Fispact-II is a code system and library database for modelling activation-transmutation processes depletion-burn-up, time dependent inventory and radiation damage source terms caused by nuclear reactions and decays. The Fispact-II code, written in object-style Fortran, follows the evolution of material irradiated by neutrons, alphas, gammas, proto…
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CCFE-PR(16)352016
Carcinogenic risks of internal exposures to alpha-emitters (except radon) are relatively poorly understood. Since exposure may occur in environmental, malicious, accidental and occupational settings, understanding consequent risks is a priority for radiation protection. An occupational study in nuclear workers addresses this need as detailed histor…
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CCFE-PR(16)312016
This paper describes a recent advances in merging/reconnection experiments in MAST, namely tomographic ion Doppler spectroscopy capability from 2013 which solves the problem of the absence of ion temperature profile measurement during the solenoid-less startup. Providing 32 channel line-integrated spectra from 0.25m< rtangential <1.1m are con…
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CCFE-PR(16)362016
A number of tools have recently been developed to study equilibrium and stability in tokamaks with pressure anisotropy. Here we apply these tools to a Mega Ampere Spherical Tokamak (MAST) discharge to calculate equilibrium, Alfven continua and eigenmodes, through to linear growth and nonlinear saturation of a toroidal Alfven eigenmode (TAE); this i…
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2016
In tungsten plasma-facing fusion reactor components, Ta is the third most abundant element formed by transmutation (after Re and Os), yet little is known about the behaviour of W-Ta alloys under irradiation and any effects Ta might have on Re clustering in W-Re-Ta alloys. In this study, W-4.5 at.%Ta, W-2 at.% Re-1 at.%Ta andW-2 at.%Re alloys were e…
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CCFE-PR(16)052016
PROCESS is a reactor systems code it assesses the engineering and economic viability of a hypothetical fusion power station using simple models of all parts of a reactor system. PROCESS allows the user to choose which constraints to impose and which to ignore, so when evaluating the results it is vital to study the list of constraints used. New …
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2016
Five ELMy H-mode Ne seeded JET pulses have been simulated with the self-consistent core-SOL model COREDIV. In this five pulse series only the Ne seeding rate was changed shot by shot, allowing a thorough study of the effect of Ne seeding on the total radiated power and of its distribution between core and SOL to be made. The increase in the simulat…
Showing 281 - 290 of 438 UKAEA Paper Results