Results 1 - 10 of 40
Results 1 - 10 of 40. Search took: 0.015 seconds
|Sort by: date | relevance|
[en] INPRO PR Assessment Methodology is focused on the possible contribution of an INS to a weapons programme in a given State. • INPRO assesses the whole INS in a specific State or region throughout the full life cycle, not only separate elements of innovative nuclear systems.
[en] Motivations for the SFR: • High potential to operate with a high conversion fast spectrum core for increasing resource utilization; • Capability of efficient and nearly complete consumption of transuranics; • High level of safety obtained by the use of innovative and reliable solutions, and, as needed or possible, inherent and passive measures; • Enhanced economics achieved with the use of high burn-up fuels, fuel cycle (e.g. disposal) benefits, reduction in power plant capital costs and lower operation costs.
[en] Possible utilization of Thorium in LWRs & Gen IV systems: 1. UTh or PuTh in LWRs without recycle. Objective: Save 235U in the open cycle mode and increase burn-up (USA, …) or Decrease amounts of plutonium to repository (Germany…). 2. UTh or PuTh with partial recycle in LWRs. 3. Symbiotic cycles « LWR/CANDU + FR » (India, GAINS, …). Objective: Use FBRs to breed 233U to fuel LWRs or CANDUs that make best utilization of it. 4. TMSR (CNRS, Europe, GEN IV, …). Objective: System optimized for the thorium cycle through minimizing parasitic captures (FP, Pa, …) – Optimum neutron balance
[en] Qualitative Safety Features Review (QSR): • The Qualitative Safety Features Review is a new tool that provides a systematic means of ensuring and documenting that the evolving Generation IV system’s design incorporates the desirable safety-related attributes and characteristics that are identified and discussed in the RSWG’s report. • Using a structured template, the QSR provides a useful preparatory step to shape designers’ approaches to their work to help ensure that safety truly is “built-in, not added-onto” since the early phases of the design of Generation IV systems.
[en] Summary: • Modelling and Simulation of nuclear reactors (advanced or otherwise) is a broad area. • Scope needs to be carefully selected: - A collaborative project has a typical duration of 2-3 years; - Define a scope that complements and is coordinated with ongoing activities (i.e., GIF). • Input from this meeting will be considered in determining final scope. • Identify key points of contact with parallel GIF activities in modelling and simulation.
[en] Main goals of the CD&S project: - Definition of a GFR reference conceptual design and operating parameters (meeting requirements on breeding, MA transmutation, Pu inventory, and safety objectives); - Identification and study of alternative design features (e.g., lower temperatures, pre-stressed concrete pressure vessel, diverse decay heat removal systems); - Definition of appropriate safety architecture for the reference GFR system and its alternatives; - Definition of the ALLEGRO conceptual design and its safety architecture, in coherence with that of the GFR; - Development and validation of computational tools needed to analyze performance and operating transients (design basis accidents and beyond).Main goals of the FCM project: → investigate fuel element design, manufacturing and qualification, material for cladding, and dense fuel material: - Develop fuel design, with at least 50% of fissile phase inside the fuel element, pin type fuel have been finally selected to enhance high power density; - For clad, standard alloys cannot reach the foreseen temperature. Refractory materials have to be envisaged (SiC ceramic composite and V alloys), while ODS alloy can be applied for lower temperature GFR core concepts; - For achieving a high power density and a high temperature, dense fuels with good thermal conductivity are required. Carbide and nitride appear more attractive than oxide. However, oxide is a back up because of a lot of experience feedback.
[en] Conclusion • Small and medium sized reactors (SMRs) may provide an attractive and affordable nuclear power option for developing countries with small electrical grids, insufficient infrastructure and limited investment capability. • Multi-module power plants with SMRs may offer energy production flexibility that energy market deregulation might call for in the future in many countries. • SMRs are of particular interest for co-generation and many advanced future process heat applications. • Some SMR designs may reduce obligations of the user for spent fuel and waste management and offer possibly greater non-proliferation assurances to the international community. • Advanced SMRs have several common technology development issues related to their targeted location in the proximity to the users, competitiveness in targeted applications, enhanced proliferation resistance and security, long refuelling interval and operation without on-site refuelling. • The Agency's role is to coordinate efforts of its Member States to facilitate the development of SMRs of various types by taking a systematic approach to the identification and development of key enabling technologies to achieve competitiveness and reliable performance of such reactors, and by addressing common infrastructure issues that could facilitate their deployment.
[en] Summary: How to consider HR, education and training from the beginning: • Use an integrated, systematic approach toward considering and implementing a NP programme (The “Milestones” Approach). • Develop workforce/staffing plans that are based upon the roles and responsibilities for the activities in each of the 3 Phases. • Develop partnerships among NP organizations, universities, and technical schools from the beginning (not just for nuc. eng). • Require SAT for all training programmes. • Include SAT, and knowledge capture and transfer requirements in supplier(s) contracts. • Maintain this integrated workforce planning approach through the entire lifecycle of the facilities/programmes.
[en] Conclusion: • Hydrogen Production PA aims at developing and optimizing H2 production processes coupled to nuclear heat source. • Four processes are presently more advanced: – Sulfur/Iodine thermochemical cycle; – High Temperature Electrolysis; – Hybrid Sulfur cycle; – Copper Chloride cycle. • Studies include all aspects from base research (thermodynamic data, materials development and behavior) to large scale experiment (e.g. DOE/CEA Lab Scale pilot for S/I cycle), and economic evaluation
[en] Strategic Goals of Technology Development Section: 1. Continuously monitor worldwide activities on technology development. 2. Facilitate exchange of information among IAEA Member States on technology development. 3. Foster international collaboration on technology development. 4. Support near term deployment of nuclear programs for both emerging and existing countries in technology development. 5. Provide technology training.