scholarly journals On the Dimensions Required for a Molten Salt Zero Power Reactor Operating on Chloride Salts

2021 ◽  
Vol 11 (15) ◽  
pp. 6673
Author(s):  
Bruno Merk ◽  
Anna Detkina ◽  
Seddon Atkinson ◽  
Dzianis Litskevich ◽  
Gregory Cartland-Glover
Keyword(s):  
Heavy Metal ◽  
Molten Salt ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Power Reactor ◽  
Modelling And Simulation ◽  
Advanced Technology ◽  
Electricity Production ◽  
Eutectic System ◽  
Low Carbon

Molten salt reactors have gained substantial interest in the last years due to their flexibility and their potential for simplified closed fuel cycle operation for massive expansion in low-carbon electricity production, which will be required for a future net-zero society. The importance of a zero-power reactor for the process of developing a new, innovative rector concept, such as that required for the molten salt fast reactor based on iMAGINE technology, which operates directly on spent nuclear fuel, is described here. It is based on historical developments as well as the current demand for experimental results and key factors that are relevant to the success of the next step in the development process of all innovative reactor types. In the systematic modelling and simulation of a zero-power molten salt reactor, the radius and the feedback effects are studied for a eutectic based system, while a heavy metal rich chloride-based system are studied depending on the uranium enrichment accompanied with the effects on neutron flux spectrum and spatial distribution. These results are used to support the relevant decision for the narrowing down of the configurations supported by considerations on cost and proliferation for the follow up 3-D analysis. The results provide for the first time a systematic modelling and simulation approach for a new reactor physics experiment for an advanced technology. The expected core volumes for these configurations have been studied using multi-group and continuous energy Monte-Carlo simulations identifying the 35% enriched systems as the most attractive. This finally leads to the choice of heavy metal rich compositions with 35% enrichment as the reference system for future studies of the next steps in the zero power reactor investigation. An alternative could be the eutectic system in the case the increased core diameter is manageable. The inter-comparison of the different applied codes and approaches available in the SCALE package has delivered a very good agreement between the results, creating trust into the developed and used models and methods.

scholarly journals Preliminary proliferation study of the molten salt fast reactor

2020 ◽  
Vol 6 ◽  
pp. 5 ◽  
Author(s):  
Michel Allibert ◽  
Elsa Merle ◽  
Sylvie Delpech ◽  
Delphine Gerardin ◽  
Daniel Heuer ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fast Reactor ◽  
Molten Salts ◽  
Fuel Cycle ◽  
Power Reactor ◽  
Nuclear Material ◽  
Reactor System ◽  
Molten Salt Reactor ◽  
International Forum ◽  
Large Power

The molten salt reactor designs, where fissile and fertile materials are dissolved in molten salts, under consideration in the framework of the Generation IV International Forum, present some unusual characteristics in terms of design, operation, safety and also proliferation resistance issues. This paper has the main objective of presenting some proliferation challenges for the reference version of the Molten Salt Fast Reactor (MSFR), a large power reactor based on the thorium fuel cycle. Preliminary studies of proliferation resistance are presented here, dedicated to the threat of nuclear material diversion in the MSFR, considering both the reactor system itself and the processing units located onsite.

scholarly journals Innovative Investigation of Reflector Options for the Control of a Chloride-Based Molten Salt Zero-Power Reactor

2021 ◽  
Vol 11 (15) ◽  
pp. 6795
Author(s):  
Bruno Merk ◽  
Anna Detkina ◽  
Seddon Atkinson ◽  
Dzianis Litskevich ◽  
Gregory Cartland-Glover
Keyword(s):  
Monte Carlo ◽  
Molten Salt ◽  
Power Distribution ◽  
Fuel Cycle ◽  
Power Reactor ◽  
Cost Savings ◽  
Monte Carlo Study ◽  
Beryllium Oxide ◽  
Negative Effects ◽  
Closed Fuel Cycle

Molten salt reactors have gained substantial interest in the last years due to their flexibility and their potential for simplified closed fuel cycle operations for massive net-zero energy production. However, a zero-power reactor experiment will be an essential first step into the process delivering this technology. The choice of the optimal reflector material is one of the key issues for such experiments since, on the one hand, it offers huge cost savings potential due to reduced fuel demand; on the other hand, an improper choice of the reflector material can have negative effects on the quality of the experiments. The choice of the reflector material is, for the first time, introduced through a literature review and a discussion of potential roles of the reflector. The 2D study of different potential reflector materials has delivered a first down-selection with SS304 as the representative for stainless steel, lead, copper, graphite, and beryllium oxide. A deeper look identified, in addition, iron-based material with a high Si content. The following evaluation of the power distribution has shown the strong influence of the moderating reflectors, creating a massively disturbed power distribution with a peak at the core boundary. This effect has been confirmed through a deeper analysis of the 2D multi-group flux distribution, which led to the exclusion of the BeO and the graphite reflector. The most promising materials identified were SS304, lead, and copper. The final 3D Monte Carlo study demonstrated that all three materials have the potential to reduce the required amount of fuel by up to 60% compared with NaCl, which has been used in previous studies and is now taken as the reference. An initial cost analysis has identified the SS304 reflector as the most attractive solution. The results of the 2D multi-group deterministic study and the 3D multi-group Monte Carlo study have been confirmed through a continuous energy Monte Carlo reference calculation, showing only minor differences.

scholarly journals Evaluating Reactivity Control Options for a Chloride Salt-Based Molten Salt Zero-Power Reactor

2021 ◽  
Vol 11 (16) ◽  
pp. 7447
Author(s):  
Bruno Merk ◽  
Anna Detkina ◽  
Seddon Atkinson ◽  
Dzianis Litskevich ◽  
Gregory Cartland-Glover
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Power Reactor ◽  
Singular System ◽  
System Level ◽  
Chloride Salt ◽  
Solid Core ◽  
Closed Fuel Cycle ◽  
The Core ◽  
Reactor Experiment

Molten salt reactors have gained substantial interest in recent years due to their flexibility and their potential for simplified closed fuel cycle operation for massive net-zero energy production. However, a zero-power reactor experiment will be an essential first step in the process of delivering this technology. The topic of the control and shutdown for a zero-power reactor is, for the first time, introduced through a literature review and a reduction in the control approaches to a limited number of basic functions with different variations. In the following, the requirements for the control and shutdown systems for a reactor experiment are formulated, and based on these assessments, an approach for the shutdown, i.e., splitting the lower part of the core with a reflector, and an approach for the control, i.e., a vertically movable radial reflector, are proposed. Both systems will be usable for a zero-power system with a liquid as well as a solid core, and even more importantly, both systems somehow work at the integral system level without disturbing the central part of the core which will be the essential area for the experimental measurements. Both approaches were investigated as a singular system, in addition to their interactions with one another and the sensitivity of the control system. This study demonstrates that both proposed systems are able to deliver the required characteristics with a sufficient shutdown margin and a sufficiently wide control span. The interaction of the system is shown to be manageable, and the sensitivity is at a very good level. The multi-group Monte Carlo approach was cross-evaluated by a continuous energy test, leading to good results, but they also demonstrate that there is room for improvement.

scholarly journals The Need for Integrating the Back End of the Nuclear Fuel Cycle in the United States of America

MRS Advances ◽  
2018 ◽  
Vol 3 (19) ◽  
pp. 991-1003 ◽  
Author(s):  
Evaristo J. Bonano ◽  
Elena A. Kalinina ◽  
Peter N. Swift
Keyword(s):  
United States ◽  
Nuclear Fuel ◽  
United States Of America ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Spent Fuel ◽  
Dry Storage ◽  
The Us

ABSTRACTCurrent practice for commercial spent nuclear fuel management in the United States of America (US) includes storage of spent fuel in both pools and dry storage cask systems at nuclear power plants. Most storage pools are filled to their operational capacity, and management of the approximately 2,200 metric tons of spent fuel newly discharged each year requires transferring older and cooler fuel from pools into dry storage. In the absence of a repository that can accept spent fuel for permanent disposal, projections indicate that the US will have approximately 134,000 metric tons of spent fuel in dry storage by mid-century when the last plants in the current reactor fleet are decommissioned. Current designs for storage systems rely on large dual-purpose (storage and transportation) canisters that are not optimized for disposal. Various options exist in the US for improving integration of management practices across the entire back end of the nuclear fuel cycle.

Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium

2022 ◽  
Vol 165 ◽  
pp. 108638
Author(s):  
Jianhui Wu ◽  
Jingen Chen ◽  
Chunyan Zou ◽  
Chenggang Yu ◽  
Xiangzhou Cai ◽  
...  
Keyword(s):  
Molten Salt ◽  
Heavy Water ◽  
Fuel Cycle ◽  
Molten Salt Reactor

Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

2014 ◽  
Author(s):  
Jiři Křepel ◽  
Valentyn Bykov ◽  
Konstantin Mikityuk ◽  
Boris Hombourger ◽  
Carlo Fiorina ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Ex Situ ◽  
Molten Salt Reactor ◽  
Inherent Safety ◽  
Neutron Spectra ◽  
Fuel Fabrication

The Molten Salt Reactor (MSR) represents an old concept, but its properties are qualifying it for the advanced utilization: inherent safety, excellent neutron economy, possibility of continuous or batch reprocessing without fuel fabrication. The aim of this paper is to characterize the MSR unique fuel cycle advantages in different neutron spectra using the results of ERANOS-based EQL3D and ECCO-MATLAB based EQL0D procedures. It also focuses on the low production of higher actinides in the Th-U cycle and based on the results, it proposes a simplified in situ recycling of the fuel and the delayed ex situ carrier salt cleaning or direct disposal by vitrification.

scholarly journals French Energy Sector in Search for Optimal Model

2019 ◽  
Vol 12 (5) ◽  
pp. 156-171
Author(s):  
A. V. Zimakov
Keyword(s):  
Power Generation ◽  
Nuclear Power ◽  
Nuclear Reactors ◽  
Current Model ◽  
Energy Transition ◽  
Clean Energy ◽  
Green Energy ◽  
Electricity Production ◽  
Low Carbon ◽  
The Eu

Clean energy transition is one of major transformation processes in the EU. There are different approaches among EU countries to decarbonization of their energy systems. The article deals with clean energy transition in France with the emphasis on power generation. While this transformation process is in line with similar developments in the EU, the Franch case has its distinct nature due to nuclear power domination in electricity production there. It represents a challenge for the current model as the transition is linked to a sharp drop of nuclear share in the power mix. It is important to understand the trajectory of further clean energy transition in France and its ultimate model. The article reviews the historical roots of the current model (which stems from Messmer plan of the 1970-es) and its development over years, as well as assesses its drawbacks and merits in order to outline possible future prospects. The conclusion is that the desired reduction of nuclear energy is linked not solely to greening process but has a complex of reasons, the ageing of nuclear reactors being one of them. Nuclear power remains an important low-carbon technology allowing France to achieve carbon neutrality by 2050. A desired future energy model in France can be understood based on the analysis of new legislation and government action plans. The targeted model is expected to balance of nuclear and green energy in the generation mix in 50% to 40% proportion by 2035, with the rest left to gas power generation. Being pragmatic, French government aims at partial nuclear reactors shut down provided that this will not lead to the rise of GHG emissions, energy market distortions, or electricity price hikes. The balanced French model is believed to be a softer and socially comfortable option of low-carbon model.

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