The Fast Breeder Reactor — Energy without Depletion of Natural Resources

1976 ◽  
Vol 190 (1) ◽  
pp. 163-175
Author(s):  
R. D. Vaughan ◽  
A. A. Farmer
Keyword(s):  
Energy Production ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Primary Energy ◽  
Western World ◽  
Fast Reactors ◽  
Generating Capacity ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Fuel Reprocessing

SYNOPSIS. Nuclear power should account for 20% of primary energy production in the Western world by the end of the century, but only if growth of generating capacity can be freed of the constraint of uranium supply. It is shown that, providing fast breeder reactors and their associated fuel reprocessing facilities are developed quickly, a substantial increase in nuclear capacity could be provided by fast reactors. The relative importance of various fuel cycle parameters is spelt out and brief accounts are given of the alternative fast reactors being developed to meet the requirements.

The Perspective of Creating a Closed Fuel Cycle Based on the Fast Reactors in Ukraine

2012 ◽  
Author(s):  
I. A. Tereshchenko ◽  
S. O. Ustimenko
Keyword(s):  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Light Water Reactors ◽  
Fast Reactors ◽  
Closed Fuel Cycle ◽  
Mox Fuel ◽  
Fast Breeder Reactors ◽  
Water Reactors ◽  
Breeder Reactors ◽  
New Generation

It is known that the IAEA considers options for a fuel cycle with light water reactors of new generation (LWR); however, the uranium reserves will not last forever, so the input of fast reactors in order to “close” the fuel cycle is currently the best option. Therefore, the preliminary calculations of the approximate cycle took place, and a comparative analysis of cycles using only LWR and the cycle with a gradual replacement of LWR by fast breeder reactors was carried out as well. It is appropriate, because there is a sufficiently large number of spent nuclear fuel now is accumulated in temporary storage, but soon it has to be either converted into fresh fuel or disposed (that is unacceptable in all respects). The main problem of the closed fuel cycle is usage of MOX-fuel, but this type of fuel is elaborated now and will be improved upon.

Site Remediation Techniques in India: A Review

2013 ◽  
Author(s):  
Anomitra Banerjee ◽  
Miller Jothi
Keyword(s):  
Contaminated Soils ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Environmental Waters ◽  
Site Remediation ◽  
Research Reactors ◽  
Hazardous Waste Sites ◽  
Advantages And Disadvantages ◽  
Fuel Reprocessing

India is one of the developing countries operating site remediation techniques for the entire nuclear fuel cycle waste for the last three decades. In this paper we intend to provide an overview of remediation methods currently utilized at various hazardous waste sites in India, their advantages and disadvantages. Over the years the site remediation techniques have been well characterized and different processes for treatment, conditioning and disposal are being practiced. Remediation Methods categorized as biological, chemical or physical are summarized for contaminated soils and environmental waters. This paper covers the site remediation techniques implemented for treatment and conditioning of wastelands arising from the operation of nuclear power plant, research reactors and fuel reprocessing units.

scholarly journals On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED

2016 ◽  
Vol 2 (4) ◽  
Author(s):  
Luigi Lepore ◽  
Romolo Remetti ◽  
Mauro Cappelli
Keyword(s):  
Monte Carlo ◽  
Neutron Flux ◽  
Fast Reactor ◽  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Signal To Noise Ratio ◽  
Reactor Power ◽  
Fast Reactors ◽  
Flux Monitoring

Among GEN IV projects for future nuclear power plants, lead-cooled fast reactors (LFRs) seem to be a very interesting solution due to their benefits in terms of fuel cycle, coolant safety, and waste management. The novelty of this matter causes some open issues about coolant chemical aspects, structural aspects, monitoring instrumentation, etc. Particularly, hard neutron flux spectra would make traditional neutron instrumentation unfit to all reactor conditions, i.e., source, intermediate, and power range. Identification of new models of nuclear instrumentation specialized for LFR neutron flux monitoring asks for an accurate evaluation of the environment the sensor will work in. In this study, thermal hydraulics and chemical conditions for the LFR core environment will be assumed, as the neutron flux will be studied extensively by the Monte Carlo transport code MCNPX (Monte Carlo N-Particles X-version). The core coolant’s high temperature drastically reduces the candidate instrumentation because only some kinds of fission chambers and self-powered neutron detectors can be operated in such an environment. This work aims at evaluating the capabilities of the available instrumentation (usually designed and tailored for sodium-cooled fast reactors) when exposed to the neutron spectrum derived from the Advanced Lead Fast Reactor European Demonstrator, a pool-type LFR project to demonstrate the feasibility of this technology into the European framework. This paper shows that such a class of instrumentation does follow the power evolution, but is not completely suitable to detect the whole range of reactor power, due to excessive burnup, damages, or gamma interferences. Some improvements are possible to increase the signal-to-noise ratio by optimizing each instrument in the range of reactor power, so to get the best solution. The design of some new detectors is proposed here together with a possible approach for prototyping and testing them by a fast reactor.

The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

2010 ◽  
Author(s):  
Guang Jun Chen ◽  
Yu Lin Cui ◽  
Guo Guo Zhang ◽  
Hong Jun Yao
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Fission Products ◽  
Purex Process ◽  
Spent Fuel ◽  
Spent Fuel Reprocessing ◽  
Long Life ◽  
Fuel Reprocessing

With an increased population and an increasing demand for power, nuclear power has attracted an increasing attention and mass nuclear power plant have been built in different countries in the past several decades. At present, about ten thousands ton spent fuels are discharged from nuclear power plant every year and the estimated capacity will approximately add up to 5×105 ton. Therefore, spent fuel reprocessing, by which the co-extraction and separation as well as purification of Uranium and Plutonium could be realized and ensure the recycle of uranium resources and the management of nuclear waste, is a vital step in nuclear fuel cycle including two major strategies, i.e. once-through cycle and closed fuel cycle. It is worth noting that the utilization of MOX fuel made by plutonium mixed with uranium has been successfully achieved in thermal reactor. Fortunately, the middle experiment plant of china spent fuel reprocessing has been being debugged and will be operated completely in future two years. Various reprocessing schemes have been proposed for the extraction of actinides from fission products and other elements presented in spent nuclear fuel. However, after numerous studies of alternate reprocessing methods and intensive searches for better solvents, the PUREX process remains the prime reprocessing method for spent nuclear fuels throughout the world. High burning and strong radioactive spent fuel resulting from the evolution of various reactors drive the development of the advanced PUREX technology, which emphasizes the separation of neptunium and technetium besides the separation of the Uranium and Plutonium from the majority of highly active fission products. In addition, through Partitioning and Transmutation method, some benefits such as segregating the actinides and long life fission products from the high level waste can be obtained. The GANEX process exploited by CEA, which roots in COEX process belonged to advanced PUREX process, considers the separation of the actinides and long life fission products. The study on the pyro-chemical processing such as the method of electro-deposition from molten salts has still not replaced the traditional PUREX process due to various reasons. In conclusion, the future PUREX process will focus on the modified process including predigesting the technical flowsheets and reducing reprocessing costs and using salt-less reagent in order to minimize the waste production.

scholarly journals Achievability of radiological equivalence associated with closed nuclear fuel cycle with fast reactors: impact of uncertainty factors in scenarios of Russian nuclear power development through to 2100. Part 1. Fast and thermal reactors

2021 ◽  
Vol 30 (2) ◽  
pp. 62-76
Author(s):  
V.K. Ivanov ◽  
◽  
A.V. Lopatkin ◽  
A.N. Menyajlo ◽  
E.V. Spirin ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy Development ◽  
Radioactive Wastes ◽  
Fast Reactors ◽  
Power Development ◽  
The Public ◽  
Radiation Risks ◽  
Nuclear Power Development

The Russian Government approved the Energy Strategy of the Russian Federation (Government Decree No.1523-r of June 9, 2020). The Strategy envisages the use of both thermal (TR) and fast (FR) reactors. The Strategy points out that the problems of nuclear power are associated with po-tential high expenses for irradiated fuel and radioactive wastes management. The previously de-signed model of the Russian nuclear energy development suggested that fast reactors only would operate at NPPs after 2010. Radiological equivalence, expressed as the equivalence of lifetime radiation risks to the public from radioactive wastes and from primary uranium ore, was shown to be achieved after 100-year storage. The burnup of 241Am, 237Np и 242Сm in closed nu-clear fuel cycle with fast reactors is a key part in the achievability of radiation risks equivalence. Scenarios of the Russian nuclear energy development through to 2100 with account of uncertain-ty factors in the measurement of contribution of fast and thermal reactors to the electric energy production are considered in the paper. The following three scenarios were developed: uncer-tainty is replaced by FRs; uncertainty is replaced by TRs; 50 per cent of FRs and 50 per cent of TRs replace uncertainty. If the energy is produced by fast reactors only (scenario 1) radiological equivalence was found to be achieved in 412 years. In two other scenarios radiological equiva-lence will be achieved after more than 1000 years. Contribution of main dose-forming radionu-clides and relevant ratios of potential biological hazards is included in models regardless of whether uncertainty in nuclear energy development is taking or not taking into account. Results of the study of conditions for radiological equivalence achievement should be used for amending Strategic plan of Russian nuclear power development through to 2100 that meets requirements of radiation ecology and radiation protection of the public.

Heavy Ion Bombardment of Stainless Steel

1970 ◽  
Vol 28 ◽  
pp. 410-411
Author(s):  
J. J. Laidler
Keyword(s):  
Stainless Steel ◽  
Fuel Cycle ◽  
Irradiation Time ◽  
Heavy Ion ◽  
Structural Components ◽  
Fuel Cladding ◽  
Fuel Cycles ◽  
Volumetric Expansion ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

A problem of current concern in the design of liquid-metal cooled, fast breeder reactors (LMFBR) for commercial power generation is the volumetric expansion of structural components due to the agglomeration of vacancies produced during irradiation. Present plans call for LMFBR fuel cladding and major structural components to be fabricated of an austenitic stainless steel; with operating temperatures and fuel cycles now anticipated, projected values of the volumetric expansion in fuel clad at the end of a fuel cycle are as high as 10-12%. The attainment of such fluences in present test reactors is costly and time-consuming, requiring an irradiation time of some 4-5 years.

Optimization of Small Long Life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input

2012 ◽  
Vol 260-261 ◽  
pp. 307-311 ◽  
Author(s):  
Menik Ariani ◽  
Z. Su'ud ◽  
Fiber Monado ◽  
A. Waris ◽  
Khairurrijal ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Volume Fraction ◽  
Natural Circulation ◽  
Average Power ◽  
Natural Uranium ◽  
Energy Utilization ◽  
Fast Reactors ◽  
Long Life

In this study gas cooled reactor system are combined with modified CANDLE burn-up scheme to create small long life fast reactors with natural circulation as fuel cycle input. Such system can utilize natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore using this type of nuclear power plants optimum nuclear energy utilization including in developing countries can be easily conducted without the problem of nuclear proliferation. In this paper, optimization of Small and Medium Long-life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input has been performed. The optimization processes include adjustment of fuel region movement scheme, volume fraction adjustment, core dimension, etc. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 75 W/cc. With such condition we investigated small and medium sized cores from 300 MWt to 600 MWt with all being operated for 10 years without refueling and fuel shuffling and just need natural Uranium as fuel cycle input. The average discharge burn-up is about in the range of 23-30% HM.

Design of 500 MWe Metal Fuel Demonstration Fast Reactor

2014 ◽  
Author(s):  
Chellapandi Perumal ◽  
V. Balasubramaniyan ◽  
P. Puthiyavinayagam ◽  
Raghupathy Sundararajan ◽  
Madhusoodanan Kanakkil ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Large Scale ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Industrial Scale ◽  
Fast Breeder Reactor ◽  
Spent Fuel ◽  
Metal Fuel ◽  
Water Reactors ◽  
Breeder Reactors

Indian nuclear power programme is being implemented in three stages taking in to consideration limited uranium resources and vast thorium resources in the country. The first stage consists of investing natural uranium in Pressurized Heavy Water Reactors (PHWR). This stage has the potential of 10 GWe. The second stage involves large scale deployment of Fast Breeder Reactors (FBR) with co-located fuel cycle facilities to utilize the plutonium and depleted uranium extracted from the PHWR spent fuel. This stage has a potential of about 300 GWe. In the third stage, effective utilization of the vast thorium resources is planned. Indira Gandhi Centre for Atomic Research (IGCAR) instituted in 1971 at Kalpakkam, is involved in the mission of developing the technology of FBR. A host of multidisciplinary laboratories are established in the centre around the central facility of the 40 MWt Fast Breeder Test Reactor (FBTR). Presently, the construction of indigenously designed MOX fueled 500 MWe Prototype Fast Breeder Reactor (PFBR) that started in 2003 is in advanced stage and commissioning activities are underway. The design of PFBR incorporates several state-of-art features and is foreseen as an industrial scale techno-economic viability demonstrator for the FBR program. Beyond PFBR, the proposal is to build one twin unit having two reactors, with each of improved design compared to PFBR, to be commissioned by 2025. Subsequently, towards rapid realization of nuclear power, the department is planning a series of metal fueled FBRs starting with a 500 MWe Metal fuel Demonstration Fast Breeder Reactor (MDFR-500) to be followed by industrial scale 1000 MWe metal fueled reactors. The paper discusses in detail the above aspects and highlights the activities carried out towards designing MDFR.

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