[en] This presentation will provide an overview of the range of tools being utilized by the U.S. DOE Fuel Cycle Options Campaign, including: -) Reactor core performance tools and databases; -) Fuel cycle analysis tools; -) Market-based analysis tools; -) Cost and financial risk analysis tools and data sets; -) Technology and fuel cycle evaluation tools; -) Collaboration and communication tools. This document is composed of an introduction and the slides of the presentation.

[en] In this series of slides it is shown how the reactor model is a key issue for fuel cycle simulation. The purpose of a reactor model is to predict first, the fuel quantity needed for the loading of this type or reactors and secondly, the spent fuel composition. It may be difficult to anticipate isotopic compositions in case of multi-recycling. Another issue is that reliable reactor models are also indispensable for studying reactor synergies when the deployment or the renewal of a fleet of reactors is considered.

[en] In this series of slides the author highlights the differences between scenarios and predictions and the importance of the assessment of uncertainties and bias for both. Scenarios are not predictions, they are rather used to demonstrate the feasibility of a strategy in a context regardless the plausibility of the context. Traditional uncertainty methods can be applied to scenarios to assess their resistance.

[en] In this short series of slides, the author presents 2 important things: first, the uncertainty about the deployment of nuclear power in the coming century in the context of an increasing energy demand and fight against climate warming and secondly the diversity of fuel cycle issues.

[en] Today, there is a lack of methods to verify baseline declarations of fissile material holdings. One method is the attempt to reconstruct the past fissile material production. This approach is called nuclear archaeology. Measurements in shutdown nuclear facilities and radioactive wastes and the assessment of neutron activation of permanent reactor components could yield additional information. To make best use of the various sources of information, including from records and measurements, new models and tools are needed. The approach we propose is a combination of forward-simulations of fuel cycle operations and inverse analysis based on measurement results, perhaps in an iterative manner. This document is composed of an introduction and the slides of the presentation.

[en] This workshop has mainly focused on the following topics: fuel cycle simulators, the uncertainty management in fuel cycle simulations, scenario studies and non-proliferation. It has been shown how the reactor model is a key issue for cycle simulation. Importance has been given to the transition scenarios from a fleet of thermal reactors to the implementation of fast reactors and the modification of the fuel cycle required for the implementation of molten salt reactors. Most documents are composed of an introduction and the slides of the presentation

[en] Nuclear fuel cycle analysis spans a wide range of systems and processes from modeling and analysis of combustions processes to understanding the nuclear industry and ecosystem at a macroscopic level. We designed a framework for analysis and visualization of multi-dimensional nuclear simulations data using a partition-based topological and geometric approach. This document is composed of an introduction and the slides of the presentation.

[en] This presentation will highlight the results of a case study analysis to identify the least cost alternatives for transitioning to a nuclear fuel cycle. The transition is from the current once-through light water reactor (LWR) low enriched uranium (LEU) oxide-based fuel cycle to a new, closed fuel cycle based on fast spectrum breakeven reactors or fast breeders and thermal burners. Four alternative scenarios and cases appear in the analysis. These are evaluated using an economic model designed to evaluate the system costs of each alternative. The cost data for the model come from the Advanced Fuel Cycle Cost Basis Report. The data on the material flows and mass balance are generated using the VISION model for simulating fuel cycle possibilities. Results suggest that the economically optimized scenarios have better cost performance than a system optimized on material flow alone. This document is composed of an introduction and the slides of the presentation. (author)

[en] DYMOND (Dynamic Model of Nuclear Development) provides time-dependent mass flows and reactor/facility profiles for future deployment scenarios, it identifies bottlenecks and shortages. Traditional MSRs (Molten Salt Reactors) are designed to have online fission product removal and online refueling. This study shows how MSRs can be modeled using system dynamics codes such as DYMOND. The continuous refueling of MSRs is inherently represented by codes based on system dynamics but approximations are required for various inputs such as burnup, cycle length, batches. This document is composed of an introduction and the slides of the presentation.

[en] The presentation covers how SITON v2.0, a dynamic, discrete facilities/discrete materials fuel cycle simulator models the events of the nuclear fuel cycle. SITON contains all facility types that are important from the point of view of natural uranium utilisation and waste management. The irradiated fuel composition is determined via burnup tables of FITXS-based burnup module. SITON tracks 52 nuclides among which 25 fission products and 27 actinides. In SITON the survey of requests and the fulfilment of requests are decoupled. This solution allows to track triggered requests in the past and ensures that all requests are taken into account at the proper time. Besides highlighting the advantages of the current modelling approach the presentation tries to address its limitations as well. This document is composed of an introduction and the slides of the presentation.