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.

Conceptual Design Study of Small 400 MWt Pb-Bi Cooled Modified Candle Burn-Up Based Long Life Fast Reactors

2014 ◽  
Vol 983 ◽  
pp. 353-356 ◽  
Author(s):  
Zaki Suud ◽  
H. Sekimoto
Keyword(s):  
Conceptual Design ◽  
Fuel Cycle ◽  
Volume Fraction ◽  
Natural Uranium ◽  
Multiplication Factor ◽  
Fast Reactors ◽  
Design Study ◽  
Accumulation Pattern ◽  
Pattern Change ◽  
Long Life

In this paper conceptual design study of modified CANDLE burn-up scheme based 400 MWt small long life Pb-Bi Cooled Fast Reactors with natural Uranium as Fuel Cycle Input has been performed. In this study the reactor cores are subdivided into 10 parts with equal volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle. For small reactor core, it is important to apply high breeding material, so that high volume fraction of 60% fuel volume fraction nitride fuel is applied. The effective multiplication factor initially at 1.005 but then continuously increases during 10 years of burn-up. The peak power density initially about 307 W/cc but then continuously decreases to 268 at the end of 10 years burn-up cycle. Infinite multiplication factor pattern change, conversion ratio pattern change, and Pu-239 accumulation pattern change shows strong acceleration of plutonium production in the first region which is located near the 10th region. Maximum discharged burn-up is 31.2% HM.

scholarly journals Optimized core design for small long-life gas cooled fast reactors with natural uranium-thorium-blend as fuel cycle input

2020 ◽  
Vol 1568 ◽  
pp. 012015
Author(s):  
M Ariani ◽  
Supardi ◽  
A Johan ◽  
F Monado ◽  
Z Su’ud ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Long Life

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.

scholarly journals Nuclear Fuel Transmutation

2021 ◽  
Author(s):  
Akbar Abbasi
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Electric Energy ◽  
Computer Code ◽  
Natural Uranium ◽  
Spent Fuel ◽  
Used Nuclear Fuel ◽  
Front End

Nuclear power plants to generates electric energy used nuclear fuel such as Uranium Oxide (UOX). A typical VVER−1000 reactor uses about 20–25 tons of spent fuel per year. The fuel transmutation of UOX fuel was evaluated by VISTA computer code. In this estimation the front end and back end components of fuel cycle was calculated. The front end of the cycle parameter are FF requirements, enrichment value requirements, depleted uranium amount, conversion requirements and natural uranium requirements. The back-end component is Spent Fuel (SF), Actinide Inventory (AI) and Fission Product (FP) radioisotopes.

The degree of attainment of radiation equivalency of highly active waste and natural uranium in the fuel cycle of nuclear power plants in Russia

Atomic Energy ◽  
1996 ◽  
Vol 81 (6) ◽  
pp. 827-832
Author(s):  
E. O. Adamov ◽  
I. Kh. Ganev ◽  
A. V. Lopatkin ◽  
V. G. Muratov ◽  
V. V. Orlov
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Highly Active ◽  
Active Waste

scholarly journals STATE AND PROSPECTS OF THE RUSSIAN URANIUM MINING AND URANIUM PROCESSING INDUSTRY IN THE CONTEXT OF WORLD DEVELOPMENT

2019 ◽  
pp. 563-574
Author(s):  
Nikolay Dolchinkov ◽  
Bonka Encheva Karaivanova –Dolchinkova
Keyword(s):  
Soviet Union ◽  
Nuclear Power ◽  
Power Plants ◽  
Oil And Gas ◽  
Fuel Cycle ◽  
Mineral Exploration ◽  
Far East ◽  
Gas Production ◽  
Natural Uranium ◽  
Oil And Gas Production

A major Russian political and economic objective is to increase exports, particularly for front-end fuel cycle services through Tenex, as well as nuclear power plants. Russia uses about 3800 tonnes of natural uranium per year. After enrichment, this becomes 190 tU enriched to 4.3% for 9 VVER-1000 reactors (at 2004, now 13), 60 tU enriched to 3.6% for 6 VVER-440s, 350 tU enriched to 2.0% for 11 RBMK units, and 6 tU enriched to 20% (with 9 tU depleted) for the BN-600. Some 90 tU recycled supplements the RBMK supply at about 2% enrichment. This RepU arises from reprocessing the used fuel from BN, VVER-440 and marine and research reactors. There is high-level concern about the development of new uranium deposits, and a Federal Council meeting in April 2015 agreed to continue the federal financing of exploration and estimation works in Vitimsky Uranium Region in Buryatia. It also agreed to financing construction of the engineering infrastructure of Mine No. 6 of Priargunsky Industrial Mining and Chemical Union (PIMCU). The following month the Council approved key support measures including the introduction of a zero rate for mining tax and property tax; simplification of the system of granting subsoil use rights; inclusion of the Economic Development of the Far East and Trans-Baikal up to 2018 policy in the Federal Target Program; and the development of infrastructure in Krasnokamensk. In June 2015 Rosgeologia signed a number of agreements to expedite mineral exploration in Russia, including one with Rosatom. It was established in July 2011 by presidential decree and consists of 38 enterprises located in 30 regions across Russia, but uranium is a minor part of its interests. Russia is engaged in international nuclear energy markets, far from the traditional sites of Eastern Europe. In June 2011, Rosatom announced that it was creating a "Rusatom" overseas company, a new structure responsible for building projects that could not benefit from them. It can be executed as a primary contractor as well as as owner of foreign capacities under a self-exploitation agreement (BOO). She actively strives for shopping in developing countries and has set up eight offices abroad. The Soviet Union also used 116 nuclear explosions (81 in Russia) for geological research, creating underground gas storage, boosting oil and gas production and excavating reservoirs and canals. Most were in the 3-10 kiloton range and all occurred 1965-88.

scholarly journals The study of capability natural uranium as fuel cycle input for long life gas cooled fast reactors with helium as coolant

2016 ◽  
Author(s):  
Menik Ariani ◽  
Octavianus Cakra Satya ◽  
Fiber Monado ◽  
Zaki Su’ud ◽  
Hiroshi Sekimoto
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Long Life

Unprotected Loss of Flow Accident in Small Long Life Gas Cooled Fast Reactor

2015 ◽  
Vol 751 ◽  
pp. 263-267
Author(s):  
Su'ud Zaki
Keyword(s):  
Nuclear Power ◽  
Cooling System ◽  
Natural Circulation ◽  
Heat Removal ◽  
Reducing Power ◽  
Inherent Safety ◽  
Fast Reactors ◽  
Transient Model ◽  
Long Life ◽  
Heat Removal System

In post Fukushima nuclear accidents inherent safety capability is necessary against some standard accidents such as unprotected loss of flow (ULOF), unprotected rod run-out transient over power (UTOP), unprotected loss of heat sink (ULOHS). Gas cooled fast reactors is one of the important candidate of 4th generation nuclear power plant and in this paper the safety analysis related to unprotected loss of flow in small long life gas cooled fast reactors has been performed. Accident analysis of unprotected loss of flow include coupled neutronic and thermal hydraulic analysis which include adiabatic model in nodal approach of time dependent multigroup diffusion equations. The thermal hydraulic model include transient model in the core, steam generator, and related systems. Natural circulation based heat removal system is important to ensure inherent safety capability during unprotected accidents. Therefore the system similar to RVACS (reactor vessel auxiliary cooling system) is investigated. As the results some simulations for small 60 MWt gas cooled fast reactors has been performed and the results show that the reactor can anticipate complete pumping failure inherently by reducing power through reactivity feedback and remove the rest of heat through natural circulations.

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