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CCFE-PR(15)552015
Modelling of nuclide densities as a function of time within magnetic confinement fusion devices such as the JET, ITER and proposed DEMO tokamaks is performed using Monte-Carlo transport codes coupled with a Bateman equation solver. The generation of reaction rates occurs either through point-wise interpolation of energy dependent tracked particle …
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CCFE-PR(15)542015
Monte Carlo particle transport (MCPT) codes are incredibly powerful and versatile tools to simulate particle behavior in a multitude of scenarios, such as core/criticality studies, radiation protection, shielding, medicine and fusion research to name just a small subset applications. However, MCPT codes can be very computationally expensive to run …
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2015
Nuclear data form the basis of the radiation transport codes used to design and simulate the behaviour of nuclear facilities, such as the ITER and DEMO fusion reactors. Typically these data and codes are biased towards fission and high-energy physics applications yet are still applied to fusion problems. With increasing interest in fusion applicati…
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CCFE-PR(15)132015
A large number of materials exist which have been labeled as low activation structural materials (LAM). Most often, these materials have been designed in order to substitute-out or completely remove elements that become activated and contribute signi cantly to shut-down activity after being irradiated by neutrons in a reactor environment. To date, …
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CCFE-PR(15)1262015
Beryllium (Be) is a precious resource with many high value uses, the low energy threshold (n,2n) reaction makes Be an excellent neutron multiplier for use in fusion breeder blankets. Estimates of Be requirements and available resources suggest that this could represent a major supply difficulty for solid-type blanket concepts. Reducing the quantity…
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CCFE-PR(15)1212015
High energy neutrons produced in future fusion reactors will cause significant transmutation reactions in the breeder blanket, including the important tritium breeding reactions. The reaction rate for a given reaction type depends on the neutron spectrum and material properties. The inventory consequences fortritium production of a solid-type breed…
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2014
EASY-II(12) is designed as a functional replacement for the previous European Activation System, EASY-2010. It has extended nuclear data and new software, FISPACT-II, written in object-style Fortran to provide new capabilities for predictions of activation, transmutation, depletion and burnup. The new FISPACT-II code has allowed us to embed many mo…
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2014
Fispact-II is an inventory code capable of performing modelling of activation, trans- mutations and burn-up induced by neutron, proton, alpha, deuteron or gamma parti- cles incident on matter. It is a completely new inventory code initially designed to be a functional replacement for Fispact-2007, but now extended to have substantially more capabil…
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2014
The DEMO Active Maintenance Facility (AMF) would be used for the storage, handling and processing of In- Vessel Components (IVC) throughout their time on site, the only exception being the time that they are installed in the vessel. It is anticipated that all handling operations associated with used components will have to be carried out using remo…
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2014
The generation of tritium in sufficient quantities is an absolute requirement for a next step fusion device such as DEMO due to the scarcity of tritium sources. A number of methods have been proposed in order to meet this requirement, however a lithium-based tritium breeding blanket that surrounds the fusion plasma is widely considered to be the mo…
Showing 21 - 30 of 45 UKAEA Paper Results