GEMINI+ project proposal will be submitted to the European Commission addressing the 2016 Euratom call for proposals (deadline October 5th, 2016). GEMINI+ project will provide a conceptual design for a high temperature nuclear cogeneration system for supply of process steam to industry, a framework for the licensing of such system and a business plan for a full scale demonstration . It will rely on modular High Temperature Gas cooled Reactor (HTGR) technology, which is a mature technology with several industrial prototypes that have been constructed and operated in the world. Therefore the time scale for the industrial deployment of such nuclear cogeneration systems is the decade. With available materials and technology, such a system can provide steam to industrial steam distribution networks presently operating on industrial sites up to 550˚C, simply substituting to fossil fuel fired cogeneration plants, without any need for adaptation of the steam distribution infrastructure or of the industrial applications. In the longer term, HTGR technology can be further developed to provide higher temperature process heat. Based on its huge thermal inertia, its refractory fuel and core structural materials, on the use of helium, which is chemically inert, as coolant, and of a specific design limited to a few hundred Megawatts, modular HTGRs have a unique intrinsic safety concept preventing in any circumstances significant degradation of the nuclear fuel and consecutive radioactive releases, with no need of any human intervention. Beyond industrial cogeneration, the flexibility, robustness and simple design of modular HTGR will allow extending application of the system developed by GEMINI+ to small isolated electric grids, to electric grids with increasing proportion of intermittent renewables, to new nuclear countries, etc.

The development of nuclear weapons and energy programmes since the 1940s have created a legacy of nuclear waste and contamination worldwide. In 2012, Sellafield Limited (named as the most hazardous nuclear site in the UK) hit the national press/media when a report by the National Audit Office highlighted the considerable challenges and spiralling costs faced by the UKs Nuclear Decommissioning Authority in taking forward the cleanup of this site. In 2012, the Fukushima Daiichi power plant and surrounding contaminated area (650 km2) also recently hit international news headlines when Tokyo Electric Power Company confirmed the accidental release of 300 tonnes of highly radioactive and concentrated waste water into the Pacific Ocean. An ice wall costing £300m has been pledged to prevent groundwater flow through the most contaminated reactor site but there are still plumes of contaminated groundwater that need to be treated and the decontamination of soil (estimated at 60 Mt) will produce even more complex liquid waste. British Nuclear Fuels invested in 30 years supply of naturally occurring zeolites (clinoptilolite) to remove aqueous Cs+ and Sr2+ from fuel cooling ponds. However, legacy and accidental waste is more complex (e.g. saline wastewater, complex and high organic soil decontamination solutions from Fukushima; and lower radionuclides concentrations and high background competing ions in Sellafield groundwater). Zeolites are inefficient under these conditions (e.g. lower sorption capacity and/or low mechanical strength), therefore, new innovative technologies are required for the safe remediation (cleanup) and entrapment (lockup) of radionuclides from these complex contaminated waters. Under complex chemical conditions, microbially-generated, rapidly produced biominerals have high metal adsorption capacity/functionality compared to natural zeolites and commercially available/laboratory grade materials, arising from their unique morphology and nanoscale properties. For example, biogenic hydroxyapatite materials (HA mass more than ten times the mass of the bacteria that produced it) have durable radionuclide adsorption capacity (up to 30 %wt for radionuclides tested: Actinides (U, Am), Sr and Co under simulated groundwater conditions, against high concentrations of competing ions (0.1-2000 mmol/L Na+, Cl-, Ca2+, Mg2+) and at wide ranging pH conditions (3-9.5); the specific nanostructured morphology of Bio-HA was shown to underlie these advantages. Bio-HA also has proven superior stability against metal remobilisation, economics, & function as compared to commercially available materials and, being biogenic will never run out or require procurement or import from other countries (enabling stable-supply and rapid-response). Additionally we have produced a new Bio-CeP material that shows great promise for Cs remediation. However, both biominerals have not been tested or applied as a permeable reactive barrier or ion exchange technology using environmental conditions found at contaminated sites. The grant will be held at the University of Birmingham, which has an established track record in nuclear research dating back to 1950s, (specifically, nowadays, in remediation, decommissioning, health monitoring and residual life prediction for existing nuclear power stations) and recently led a Policy Commission into the future of nuclear energy in the UK. The grant will also be supported by the National Nuclear Laboratory and the Japanese Atomic Energy Authority enabling the achievement of technology readiness level four, rapid worldwide dissemination of research outcomes and increased societal impact.

In the current state of maturity of severe accident codes in terms of phenomena addressed and extensive validation conducted, the time has come to foster BEPU,Best Estimate Plus Uncertainties, application in the severe accident (SA) domain, and accident management (AM). The advantages with respect to deterministic analysis are known: avoid adopting conservative assumptions in the model and allow identifying safety margins, quantify likelihood of reaching specific values and, through the distribution variance provide insights into dominating uncertain parameters.The overall objective of the Management and Uncertainties of Severe Accident (MUSA) project is to assess the capability of SA codes when modelling reactor and SFP (Spent Fuel Pool) accident scenarios of Gen II and III. To do so UQ (Uncertainty Quantification) methods are to be used, with emphasis on the effect of already-set and innovative accident management measures on accident unfolding, particularly those related to ST (Source Term) mitigation. Therefore, ST related Figures Of Merit (FOM) are to be used in the UQ application. The MUSA project proposes an innovative research agenda in order to move forward the predictive capability of SA analysis codes by combining them with the best available/improved UQ tools and embedding accident management as an intrinsic aspect of SA analyses.MUSA develops through key activities which also describe the main outcomes foreseen from the project: identification and quantification of uncertainty sources in SA analyses; review and adaptation of UQ methods; and testing such methods against reactor and SFP accident analyses, including AM. Given the focus of FOM on source term, the project will identify variables governing ST uncertainties that would be worth investigating further. All the ingredients necessary to conduct the project are already available: analytical tools, experimental data, postulated reactor and SFP scenarios and, technical and scientific competences.