scholarly journals The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles

2009 ◽  
Vol 2009 ◽  
pp. 1-13 ◽  
Author(s):  
Guido Mazzini ◽  
Eleonora Bomboni ◽  
Nicola Cerullo ◽  
Emil Fridman ◽  
Guglielmo Lomonaco ◽  
...  

Nowadays nuclear is the only greenhouse-free source that can appreciably respond to the increasing worldwide energy demand. The use of Thorium in the nuclear energy production may offer some advantages to accomplish this task. Extensive R&D on the thorium fuel cycle has been conducted in many countries around the world. Starting from the current nuclear waste policy, the EU-PUMA project focuses on the potential benefits of using the HTR core as a Pu/MA transmuter. In this paper the following aspects have been analysed: (1) the state-of-the-art of the studies on the use of Th in different reactors, (2) the use of Th in HTRs, with a particular emphasis on Th-Pu fuel cycles, (3) an original assessment of Th-Pu fuel cycles in HTR. Some aspects related to Thorium exploitation were outlined, particularly its suitability for working in pebble-bed HTR in a Th-Pu fuel cycle. The influence of the Th/Pu weight fraction at BOC in a typical HTR pebble was analysed as far as the reactivity trend versus burn-up, the energy produced per Pu mass, and the Pu isotopic composition at EOC are concerned. Although deeper investigations need to be performed in order to draw final conclusions, it is possible to state that some optimized Th percentage in the initial Pu/Th fuel could be suggested on the basis of the aim we are trying to reach.

2014 ◽  
Vol 37 (2) ◽  
pp. 68-76 ◽  
Author(s):  
G. G. Geletukha ◽  
T. A. Zheliezna ◽  
P. P. Kucheruk ◽  
Ye. N. Oliinyk ◽  
O. V. Tryboi

The paper covers state of the art and outlook for bioenergy development in the EU. Potential of biomass available for energy production in Ukraine is assessed. Dynamics of the biomass potential over years is analyzed.


Author(s):  
M. Khoroshev ◽  
F. Depisch ◽  
S. Subbotin

The IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) can be considered as the IAEA’s response to the challenges of growing energy demand. INPRO’s activities are intended to help to achieve one of the main objectives of the IAEA — to promote the development and peaceful use of nuclear energy. INPRO applies a carefully developed Methodology to assess Innovative Nuclear Energy Systems (INS) and to define R&D needs and deployment strategies for the development of large-scale regional and global INS. The purpose is to match the opportunities and challenges of sustainable energy supply provided by nuclear energy (NE) to the global balance of demands and resources.


2020 ◽  
Vol 25 (2) ◽  
Author(s):  
Letícia Caroline Gonçalves ◽  
José Rubens Maiorino

In this work, the use of natural resources was analyzed using a simplified methodology and assuming calculation conditions close to the real ones, to assess the sustainability of the nuclear source and the efficiency in the use of these resources. For the analysis of open fuel cycles, four reactors were selected, these being the Pressurized Water Reactor (PWR) and Pressurized Heavy Water Reactor (PHWR), two Generation II reactors commonly used until today, the advanced Generation III reactor AP1000 and the conceptual reactor AP-Th 1000. For closed fuel cycles, the variation of the utilization of the natural resource alongside with the variation of the conversion factor were evaluated, parameterized by the burnup. It was observed that the Generation II reactors use only 1% of the natural resources and, despite technological advances, the Generation III reactor did not show a significant increase in comparison to the former. Although the closed fuel cycle includes recycling the burnt fuel from thermal reactors, it exploits only about 10% of the resources. Major improvements are observed in Fast Breeder Reactors, being able to obtain a use of almost 100% with the increase of the burning and the minimization of losses. Although the feasibility of using thorium as a nuclear fuel has been proven, it would be better used in a closed cycle, as in the self-sustainable Liquid Fluoride Thorium Reactor (LFTR), a Generation IV reactor that can transform the nuclear energy in a sustainable and renewable source of energy.


2020 ◽  
Vol 6 (4) ◽  
pp. 243-247
Author(s):  
Anton S. Lapin ◽  
Aleksandr S. Bobryashov ◽  
Victor Yu. Blandinsky ◽  
Yevgeny A. Bobrov

For 60 years of its existence, nuclear energy has passed the first stage of its development and has proven that it can become a powerful industry, going beyond the 10% level in the global balance of energy production. Despite this, modern nuclear industry is capable of producing economically acceptable energy only from uranium-235 or plutonium, obtained as a by-product of the use of low enriched uranium for energy production or surplus weapons-grade plutonium. In this case, nuclear energy cannot claim to be a technology that can solve the problems of energy security and sustainable development, since it meets the same economic and ‘geological’ problems as other technologies do, based on the use of exhaustible organic resources. The solution to this problem will require a new generation of reactors to drastically improve fuel-use characteristics. In particular, reactors based on the use of water cooling technology should significantly increase the efficiency of using U-238 in order to reduce the need for natural uranium in a nuclear energy system. To achieve this goal, it will be necessary to transit to a closed nuclear fuel cycle and, therefore, to improve the performance of a light-water reactor system. The paper considers the possibility of using a reactor with a fast-resonance neutron spectrum cooled by supercritical water (SCWR). The SCWR can be effectively used in a closed nuclear fuel cycle, since it makes it possible to use spent fuel and discharge uranium with a small amount of plutonium added. The authors discuss the selected layout of the core with a change in its size as well as the size of the breeding regions (blankets). MOX fuel with an isotopic plutonium content corresponding to that discharged from the VVER-1000 reactor is considered as fuel. For the selected layout, a study was made of the reactor system features. Compared with existing light-water reactors, this reactor type has increased fuel consumption due to its improved efficiency and nuclear fuel breeding rate up to 1 and above.


Author(s):  
Barbara Vezzoni ◽  
Giuseppe Forasassi

This work focuses on the definition of a suitable methodology to compare different nuclear energy options, with particular attention to strategies able to minimize nuclear wastes. In order to set possible transition scenarios from actual GEN-II reactors, the energy demand and the nuclear energy share up to 2050 have been evaluated by means of data available in the international literature. To compare the different options, major indicators of energy-electricity sector have been analyzed. With particular attention to nuclear energy social acceptability the major indicators investigated are the inventory and the radiotoxicity vs. time of residual wastes. In order to reach a final equilibrium situation, transition scenarios, where GEN-III (e.g. EPR) and GEN-IV new reactors (as lead cooled fast ones), have been analyzed. As cases study Spain and France scenarios have been considered.


Author(s):  
J. C. Kuijper

The PUMA project, a Specific Targeted Research Project (STREP) of the European Union EURATOM 6th Framework Program, is mainly aimed at providing additional key elements for the utilisation and transmutation of plutonium and minor actinides (neptunium and americium) in contemporary and future (high temperature) gas-cooled reactor design, which are promising tools for improving the sustainability of the nuclear fuel cycle. PUMA would also contribute to the reduction of Pu and MA stockpiles and to the development of safe and sustainable reactors for CO2-free energy generation. The project runs from September 1, 2006 until August 31, 2009. PUMA also contributes to technological goals of the Generation IV International Forum. It contributes to developing and maintaining the competence in reactor technology in the EU and addresses European stakeholders on key issues for the future of nuclear energy in the EU. An overview is presented of the status of the project at mid-term.


MRS Bulletin ◽  
2008 ◽  
Vol 33 (4) ◽  
pp. 327-337 ◽  
Author(s):  
Baldev Raj ◽  
M. Vijayalakshmi ◽  
P.R. Vasudeva Rao ◽  
K.B.S. Rao

AbstractGlobal energy demand is expected to increase steeply, creating an urgent need to evolve a judicious global energy policy, exploiting the potential of all available energy resources, including nuclear energy. With increasing awareness of environmental issues, nuclear energy is expected to play an important role on the energy scenario in the coming decades. The immediate thrust in the science and technology of nuclear materials is to realize a robust reactor technology with associated fuel cycle and ensure the cost competitiveness of nuclear power and to extend the service life of reactors to 100 years. Accordingly, the present-generation materials need to be modified to meet the demands of prolonged exposure to irradiation and extended service life for the reactor. Emerging nuclear systems incorporate features to ensure environmental friendliness, effective waste management, enhanced safety, and proliferation resistance and require development of high-temperature materials and the associated technologies. Fusion, on a longer horizon of about fve decades, also requires the development of a new spectrum of materials. The development of next-generation materials technology is expected to occur in short times and is likely to be further accelerated by strong international collaborations.


Author(s):  
Achim Brunnengräber ◽  
Lutz Mez

In no country in which nuclear energy is produced there has been elaborated satisfying solutions for nuclear waste. Since the beginning of this form of energy production, the related immense problems have been downplayed and banalised. The policy of the German governments in the last decades corresponds to this overall picture, and only the last years have seen new initiatives on the national and the EU level, reflecting the growing awareness of this extremely „wicked problem“. Nevertheless, the nuclear industry has until now been successful in refusing its responsibility and externalizing potential risks and costs. Without sufficient public pressure the entanglement between this industry and official bodies will continue and further hinder any constructive solution.


Author(s):  
M. Carreter ◽  
M. Gray ◽  
E. Falck ◽  
A. Bonne ◽  
M. Bell

The objective of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) is to support the safe, sustainable, economic and proliferation resistant use of nuclear technology to meet the needs of the 21st century. The first part of the project focusses on the development of an understanding of the requirements of possible users of innovative concepts for reactors and fuel cycle applications. This paper reports progress made on the identification of user requirements as they relate to the environment and environmental protection. The user requirements being formulated are intended to limit adverse environmental effects from the different facilities involved in the nuclear fuel cycles to be well below maximum acceptable levels. To determine if the user requirements are met, it is necessary to identify those factors that are relevant to assessment of the environmental performance of innovative nuclear systems. To this effect, Environmental Impact Assessment (EIA) and the Material Flow accounting (MFA) methodologies are being appraised for the suitability for application. This paper develops and provides the rationale for the “users’ requirements” as they are currently defined. Existing Environmental Impact Assessment and Materials Flow Accounting methodologies that can be applied to determine whether or not innovative technologies conform to the User Requirements are briefly described. It is concluded that after establishing fundamental principles, it is possible to formulate sets of general and specific users’ requirements against which, the potential adverse environmental effects to be expected from innovative nuclear energy systems (INES) can be assessed. The application of these users’ requirements should keep the adverse environmental effects from INES’s within acceptable limits.


Author(s):  
Galina Fesenko ◽  
Vladimir Kuznetsov ◽  
Vladimir Usanov

The International Atomic Energy Agency’s (IAEA’s) International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 with the goal to ensure a sustainable nuclear energy supply to meet the global energy needs in the 21st century. The INPRO activities on global and regional nuclear energy scenarios provide newcomers and mature nuclear countries alike with better understanding of options for making a collaborative transition to future sustainable nuclear energy systems. Collaborative project GAINS (Global Architecture of Innovative Nuclear Energy Systems Based on Thermal and Fast Reactors Including a Closed Fuel Cycle) developed an internationally verified analytical framework for assessing such transition scenarios. The framework (hereafter, GAINS framework) is a part of the integrated services provided by IAEA to Member States considering initial development or expansion of their nuclear energy programmes. The paper presents major elements of the analytical framework and selected results of its application, including: • Long-term nuclear energy demand scenarios based on the IAEA Member States’ high and low estimations of nuclear power deployment until 2030 and expected trends until 2050 and on forecasts of competent international energy organizations; • Heterogeneous world model comprised of groups of non-personified non-geographical countries (NGs) with different policy regarding nuclear fuel cycle back end; • Architectures of nuclear energy systems; • Metrics and tools for the assessment of dynamic nuclear energy system evolution scenarios regarding sustainability, including a set of key indicators and evaluation parameters; • An internationally verified database with best estimate material flow and economic characteristics of existing and advanced nuclear reactors and associated nuclear fuel cycles needed for material flow analysis and comparative economic analysis, extending the previously developed IAEA databases and taking into account preferences of different countries; • Selected results of sample analysis for scenarios involving transition from the present fleets of nuclear reactors and fuel cycles to future sustainable nuclear energy system architectures involving innovative technological solutions.


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