A. Valentine T. Berry S. Bradnam H. Chohan T. Eade C. Grove J. Hagues K. Hearn J. Hodson K. Lennon J. Naish J. Neilson C. Nobs L. Packer A. Turner T. Turner L. Woodall R. Worrall
Global research programmes seeking to achieve a commercially viable model of a fusion power plant are being accelerated at an unprecedented rate. One critical element to the design and licensing is an accurate understanding of the radiation environment throughout the plant lifetime and subsequent decommissioning phase. The radiation field which res…
PreprintAlex Valentine Thomas Berry Steven Bradnam James Hagues James Hodson
The accurate and efficient mapping of the radiation environment in a nuclear fusion reactor requires the most advanced radiation transport tools. The Monte Carlo method has long been deployed to deal with the complexity of fusion relevant geometries, with MCNP the adopted industry standard code among the European and wider international community. …
PreprintA.Valentine R. Worrall
Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powerful simulation code for nuclear systems analysis. Originally developed for reactor physics applications, the scope of the code now extends to coupled multi-physics simulations and radiation transport. The latter has allowed adoption of the code by t…
PreprintA.Valentine N.Fonnesu B.Bienkowska E.Laszynska D.Flammini R.Villari G.Mariano T.Eade T.Berry L.Packer
As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion technology and its viability for electricity production. The central requirements for DEMO rest on its capability to generate significant net electric power to the grid (300MW to 500 MW) safely and consistently. Plant availability and lifetime will approach that of a…
Preprint PublishedA. Valentine B. Colling R. Worrall J. Leppänen
Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, such as shielding, material lifetime and remote maintenance requirements/scheduling. Neutronics studies are performed using radiation transport codes such as MCNP, TRIP…
Preprint PublishedTim Eade Bethany Colling Jonathan Naish Lee Packer Alex Valentine
Shutdown dose rate calculations provide an essential input to the design and research of fusion power plant technology. They allow the estimation of dose to personnel and equipment during planned and unplanned maintenance. The mesh coupled rigorous 2 step (MCR2S) methodology used at Culham Centre for Fusion Energy (CCFE) was originally developed to…
Preprint Published