3. Core Layout The core loading pattern for the proliferation resistant advanced transuranic transmuting design (PRATT) was optimized to obtain an even.

Slides:



Advertisements
Similar presentations
Generation IV international Forum Overall Mission :
Advertisements

Fynan, Mar, Sirajuddin Sodium-Cooled Fast Reactor First Preliminary Report: Fuel Composition Analysis.
Constellation Energy “The Way Energy Works” PWR Tritium Issues G. C. Jones.
Lesson 17 HEAT GENERATION
EMERALD1: A Systematic Study of Cross Section Library Based Discrepancies in LWR Criticality Calculations Jaakko Leppänen Technical Research Centre of.
The Nuclear Fuel Cycle. Presentation Components of the Fuel Cycle Front End Service Period (conversion of fuel to energy in a reactor) Back end Storage.
Neutronic simulation of a European Pressurised Reactor O.E. Montwedi, V. Naicker School of Mechanical and Nuclear Engineering North-West University Energy.
Nucular Waste A Technical Analysis Ian Baird 5/12/08.
L. Tassan-Got – IPN Orsay Nuclear data and reactor physics Radiotoxicity and spent fuel.
Nuclear Energy. Possible Exam Questions 1.Compare the environmental effects of coal combustion and conventional nuclear fission for the generation of.
The Future of Nuclear Waste Management, Storage, and Disposal Thanassi Lefas 26 November 2008 ChE 359 Energy Technology and Policy.
Indian strategy for management of spent fuel from Nuclear Power Reactors S.Basu, India.
Clean and Sustainable Nuclear Power
Nuclear Energy Targets: Explain how the nuclear fuel cycle relates to the true cost of nuclear energy and the disposal of nuclear waste. Describe the issues.
А Е Ц “К О З Л О Д У Й” - Е А Д N P P K O Z L O D U Y – P L C 17 th Symposium of AER Y alta, Crimea, September 24-28, 2007 WWER-1000 SPENT FUEL NUCLIDE.
Fundamentals of Neutronics : Reactivity Coefficients in Nuclear Reactors Paul Reuss Emeritus Professor at the Institut National des Sciences et Techniques.
USE OF VVER SPENT FUELS IN A THORIUM FAST BREEDER P. Vértes, KFKI Atomic Energy Research Institute, Budapest, Hungary 17 th AER Symposium Yalta,
Fusion-Fission Hybrid Systems
核工程计算物理实验室 Nuclear Engineering Computational Physics The Neutronics Studies of Fusion Fission Hybrid Power Reactor Youqi Zheng Ph. D Nuclear.
Why are you trying so hard to fit in, when you were born to stand out?
The Nuclear Fuel Cycle Dr. Okan Zabunoğlu Hacettepe University Department of Nuclear Engineering.
Logo. ﴿قَالُواْ سُبْحَانَكَ لاَعِلْمَ لَنَا إِلاَّ مَاعَلَّمْتَنَا إِنَّكَ أَنتَ الْعَلِيمُ الْحَكِيمُ﴾ بسم الله الرحمن الرحيم.
Complex Approach to Study Physical Features of Uranium Multiple Recycling in Light Water Reactors A.A. Dudnikov, V.A. Nevinitsa, A.V. Chibinyaev, V.N.
Can Thermal Reactor Recycle Eliminate the Need for Multiple Repositories? C. W. Forsberg, E. D. Collins, C. W. Alexander, and J. Renier Actinide and Fission.
Thorium for Use in Plutonium Disposition, Proliferation Resistant Fuels, and Future Reactors Brian Johnson WISE 2006
Nuclear Fuels Storage & Transportation Planning Project Office of Fuel Cycle Technologies Nuclear Energy Criticality Safety Assessment for As-loaded Spent.
Department of Mechanical and Nuclear Engineering Reactor Dynamics and Fuel Management Group Comparative Analysis of PWR Core Wide and Hot Channel Calculations.
1 prezentácia VUJE, Inc., Okružná 5, Trnava, Slovak Republic K. Klučárová, J. Remiš, M. Závodský, V. Petényi VUJE, Inc. 17th Symposium of AER, Sept.
1 Massimo SALVATORESiemtp 8 – November th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation University.
5Ws Activity Features of Nuclear Reactors. The nuclear reactor Control rods Moderator and coolant (water) Steel vessel Fuel pins Pump Concrete shield.
1 RRC KI Reduced leakage 17th Symposium of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007, Yalta, Crimea, Ukraine ADVANCED FUEL CYCLES.
D J Coates, G T Parks Department of Engineering, University of Cambridge, UK Actinide Evolution and Equilibrium in Fast Thorium Reactors UNTF 2010 University.
Advanced Heavy Water Reactor Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA.
FAST MOLTEN SALT REACTOR –TRANSMUTER FOR CLOSING NUCLEAR FUEL CYCLE ON MINOR ACTINIDES A.Dudnikov, P.Alekseev, S.Subbotin.
RELAP5 Analyses of a Deep Burn High Temperature Reactor Core
AERB Safety Research Institute 1 TIC Benchmark Analysis Subrata Bera Safety Research Institute (SRI) Atomic Energy Regulatory Board (AERB) Kalpakkam –
USE OF THE AXIAL BURNUP PROFILE AT THE NUCLEAR SAFETY ANALYSIS OF THE VVER-1000 SPENT FUEL STORAGE FACILITY IN UKRAINE Olena Dudka, Yevgen Bilodid, Iurii.
Physics Design of 600 MWth HTR & 5 MWth Nuclear Power Pack Brahmananda Chakraborty Bhabha Atomic Research Centre, India.
Kayla J. Sax MPhil Candidate in Engineering Department of Engineering, University of Cambridge Supervised by Dr. Geoff T. Parks Investigating the Scope.
Fundamentals of Nuclear Power
MASSIMO (Measurements in Adapted Spectra of Spectral Indices and Material Oscillations): A Proposed Experimental Campaign at the NRAD Reactor.
Potential role of FF hybrids Massimo Salvatores CEA-Cadarache- France Fusion-Fission Hybrids have a potential role (in principle and independently from.
A U.S. Department of Energy Office of Science Laboratory Operated by The University of Chicago Nuclear Engineering Division Argonne National Laboratory.
1/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia Plutonium and MA Management in VVER-440 and FR P. Dařílek, R. Zajac – VUJE Trnava
Status of Attila for the Advanced Test Reactor (ATR) D. Scott Lucas INL.
2016 January1 Nuclear Options for the Future B. Rouben McMaster University EP4P03_6P03 Nuclear Power Plant Operation 2016 January-April.
1 State Scientific and Technical Center on Nuclear and Radiation Safety THE THERMAL-MECHANICAL BEHAVIOR OF FUEL PINS DURING POWER'S MANEUVERING REGIME.
COMPARATIVE ANALYSIS OF DIFFERENT METHODS OF MODELING OF MOST LOADED FUEL PIN IN TRANSIENTS Y.Ovdiyenko, V.Khalimonchuk, M. Ieremenko State Scientific.
Sources of Radiation Research Reactors
Adonai Herrera-Martínez, Yacine Kadi, Geoff Parks, Vasilis Vlachoudis High-Level Waste Transmutation: Thorium Cycle vs Multi-Tier Strategy.
NEAR-COMPLETE TRANSURANIC WASTE INCINERATION IN THORIUM-FUELLED LIGHT WATER REACTORS Ben Lindley.
ADS Activities at Argonne National Laboratory Yousry Gohar Argonne National Laboratory Proton Accelerators for Science and Innovation Workshop FERMILAB,
D J Coates, G T Parks Department of Engineering, University of Cambridge, UK Actinide Evolution and Equilibrium in Thorium Reactors ThorEA Workshop Trinity.
Nuclear Energy. Nuclear Fission We convert mass into energy by breaking large atoms (usually Uranium) into smaller atoms. Note the increases in binding.
1/10 VUJE, Inc., Okružná 5, Trnava, Slovakia; FEI STU, Ilkovičova 3, Bratislava, Slovakia Thorium Fuel Cycle Under VVER and PWR Conditions.
Nuclear Radiation NC Essential Standard Types of Radiation, Penetrating Ability of Radiation, Nuclear Equations, Nuclear Decay, Half-Life, Fission.
ADSR08 Thorium Fuel Rods Bob Cywinski School of Applied Sciences University of Huddersfield ThorEA ADSR Workshop Cambridge 13 January 2009.
THE NUCLEAR FUEL CYCLE. The Nuclear Fuel Cycle consists of sequence of steps in which U ore is mined, milled, enriched, and fabricated into nuclear fuel.
Study on Neutronics of plutonium and Minor Actinides Transmutation in Accelerator Driven System Reactor By Amer Ahmed Abdullah Al-Qaaod Ph.D student Physics.
CHEM 312: Lecture 16 Radiochemistry in reactors Part 2
In-core fuel management
CHEM 312: Lecture 19 Forensics in Nuclear Applications
Date of download: 11/7/2017 Copyright © ASME. All rights reserved.
Plant Vogtle Units 3 and 4 Alex Thirkell.
Pebble Bed Reactors for Once Trough Nuclear Transmutation
LOW-POWER RESEARCH REACTOR FOR EDUCATION AND TRAINING
Improvements of Nuclear Fuel Cycle Simulation System (NFCSS) at IAEA
3rd Workshop on dynamic fuel cycle Timothée Kooyman, DEN,DR,SPRC,LE2C
Nuclear Energy.
TRANSPORTATION CASK AND CONCRETE MODULE DESIGN FOR MANAGING NUCLEAR SPENT FUEL PRODUCED IN BUSHEHR NUCLEAR POWER PLANT A.M. TAHERIAN Iran Radioactive Waste.
Presentation transcript:

3. Core Layout The core loading pattern for the proliferation resistant advanced transuranic transmuting design (PRATT) was optimized to obtain an even power distribution which increases the cycle length and improves safety. The periphery of the core is loaded with the highest enriched assemblies while the inner region is composed primarily of two different assemblies, both with lower enrichments in a modified checker board pattern. Figure 3: Core loading pattern. Thorium-Based Mixed-Oxide Fuel for the Consumption of Transuranic Elements in Pressurized Water Reactors Jason Haas, Brock Palen, Crystal Thrall Assembly Number Assemblies per Core Pu wt% Pin 1 Pu wt% Pin U wt% Pin resistance by burning reactor grade plutonium and other long lived radioisotopes taken from spent nuclear fuel. The plutonium-thorium-uranium fuel is designed for existing Westinghouse pressurized water reactors to ensure economic feasibility and short term implementation. 1. Objective The goal of this fuel cycle is to reduce both the time and size requirements on nuclear waste storage facilities while increasing proliferation 2. Assembly Design Each assembly design is similar to the figures below with only slight enrichment and pin position modifications. Integral fuel burnable absorber (IFBA) coatings were placed on some pins to even the power level throughout the cycle length. The design is a heterogeneous 17x17 array. Figure 1: Map for assemblies 1, 2 and 4. Figure 2: Map for assemblies 6 and 7. ( 235 U, 238 U, Th)O 2 pins with low enriched 235 U. (Th, Pu)O 2 pins with low enriched reactor grade Pu. (Th, Pu)O 2 pins with moderate enriched reactor grade Pu. Minor actinide oxide pin Guide tubes 4. Cycle Length and Inventory Change Soluble boron is added to control excess reactivity and ensures a multiplication factor of 1. The maximum cycle length is determined by zero boron concentration. Minimizing the boron concentration increases operational safety. The PRATT design is compared below with the current Westinghouse reactor the AP1000. Comparison of the isotopic inventory change in units of kilograms over one cycle length, 20 MWd/kgHM, shows the PRATT design accomplishes its goals of a net consumption of transuranics, Pu and Np specifically. The hot channel factor is defined as the ratio of the maximum to average heat flux in the core. Regulations state that this ratio needs to be less than 2.5. The overall relative power, shown below, depicts the movement of radial and axial power throughout the cycle length. The radial power distribution is nearly uniform at the beginning of the fuel cycle and moves inward while the axial power rises with burnup. 5. Relative Power 6. Conclusions -Net reduction of long-lived radioisotopes kg of Pu destroyed per cycle kg of 237 Np destroyed per cycle. -Operational safety increase by a low boron concentration and low hot channel factors.