Team 16: The Nuclear Family EN-FISSIONING A SUSTAINABLE FUTURE

Similar documents
Molten Salt Reactor Technology for Thorium- Fueled Small Reactors

A Brief History of Molten Salt Reactors

Online Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor

Liquid Fueled Reactors: Molten Salt Reactor Technology

Project Proposal and Feasibility Study

Molten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor

DESIGN AND SAFETY- SUPPORT ANALYSES OF AN IN-PILE MOLTEN SALT LOOP IN THE HFR

The DMSR: Keeping it Simple

Molten-Salt Reactor FUJI and Related Thorium Cycles

Final Report. Team 16: The Nuclear Family. Meredy Brichford Christina Headley Joel Smith Thane Symens. Engineering 340 Senior Design Project

Chemical Engineering 412

Thorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR

Molten Fluorides as Power Reactor Fuels 1

Nuclear Energy Revision Sheet

Molten Salt Reactors

Module 12 Generation IV Nuclear Power Plants. Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria

ThorCon Breeder Reactor Design

Nuclear power. ME922/927 Nuclear 1

Molten Salt Reactors (MSRs)

Neutronic and Fuel Cycle Consideration: from Single Stream to Two Fluid Th-U Molten Salt System. Olga S. Feinberg

Electromagnetic flowmeter, 861 Electromagnetic pumps, 844 characteristics, 845 efficiency, 845 End blanket effects, 869 Energy costs, summary, 921 Eng

This description was taken from the Advances in Small Modular Reactor Technology Developments 2016 Edition booklet.

FJ/OH The 2004 Frédéric JOLIOT & Otto HAHN Summer School. August 25 September 3, 2004 CADARACHE, France TOPIC 2 THE REACTORS AND THEIR FUELS

The Advanced High-Temperature Reactor: High-Temperature Fuel, Molten Salt Coolant, and Liquid-Metal-Reactor Plant.

Thorium in de Gesmolten Zout Reactor

THE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969

A Summary of Generation IV Non-Classical Nuclear Systems

Liquid Fluoride Reactors: A Luxury of Choice

Practical Aspects of Liquid-Salt-Cooled Fast-Neutron Reactors

The US Fast Breeder Reactor Development Programme

UNIT-5 NUCLEAR POWER PLANT. Joining of light nuclei Is not a chain reaction. Cannot be controlled

The Tube in Tube Two Fluid Approach

Abundant and Reliable Energy from Thorium. Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015

Reactor Technology --- Materials, Fuel and Safety

MOLTEN-SALT REACTOR CONCEPTS WITH REDUCED POTENTIAL FOR PROLIFERATION OF SPECIAL NUCLEAR MATERIALS

CANDU Fundamentals. Table of Contents

Preliminary Results of Three Dimensional Core Design in JAPAN

Reaktor Nuklir Generasi IV

Advanced Reactors Mission, History and Perspectives

CONCEPTUAL DESIGN OF A POOL TYPE MOLTEN SALT BREEDER REACTOR

Denatured Molten Salt Reactors (DMSR): An Idea Whose Time Has Finally Come? Abstract

compounds thermal expansion using high temperature X-ray diffraction, as well as calorimetric measurements (Differential Scanning Calorimetry,

Supercritical Water-Cooled Reactor (SCWR) Development through GIF Collaboration

Generation IV Water-Cooled Reactor Concepts

Workshop on PR&PP Evaluation Methodology for Gen IV Nuclear Energy Systems. Tokyo, Japan 22 February, Presented at

The role of Thorium for facilitating large scale deployment of nuclear energy

Molten Salt Reactors and the Oil Sands: Odd Couple or Key to North American Energy Independence?

EM 2 : Nuclear Power for the 21 st Century

FHRs and the Future of Nuclear Energy

Basic neutronics and dynamics of graphite moderated LEU fueled MSRs

Vectorized quadrant model simulation and spatial control of Advanced Heavy Water Reactor (AHWR)

Review of R&D of thorium molten-salt reactor

2012 Deep River Science Academy Summer Lecture GENERATION IV SUPERCRITICAL WATER-COOLED REACTOR

Module 15 Advanced Reactors LWR 3+ Generation IV

-What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES?

Balance of Plant Requirements and Concepts for Tokamak Reactors

A Survey of Power Plant Designs

Generation IV Reactors

Japan Revival Strategy by Thorium MSR


TOPIC: KNOWLEDGE: K1.01 [2.5/2.5]

INAC-ENFIR Recife, November Molten Salt Nuclear Reactors

LOS ALAMOS AQUEOUS TARGET/BLANKET SYSTEM DESIGN FOR THE ACCELERATOR TRANSMUTATION OF WASTE CONCEPT

Design of MSR primary circuit with minimum pressure losses

Basic dynamics of graphite moderated LEU fueled MSRs

Science of Nuclear Energy and Radiation. Nuclear Reactor Concepts. by Dr. Jerry M. Cuttler, PEng

Transmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar

(This paper was taken from Terrestrial Energy s web site June )

Overview of GEN IV Demonstration Projects in China Jiashu, TIAN, EG Member China National Nuclear Corporation

THE KNOWN UNKNOWNS OF MOLTEN SALT REACTORS

Nuclear Fuel Cycle Lecture 8: Reactor Concepts

The Longer-Term Option: The Advanced High-Temperature Reactor

Power Stations Nuclear power stations

Advanced Fuel CANDU Reactor. Complementing existing fleets to bring more value to customers

URANIUM-THORIUM LIQUID-SALT REACTOR FOR PRODUCING VALUABLE RADIOISOTOPES

FOR A FUTURE WE CAN BELIEVE IN. International Thorium Energy Conference 2015

VALLIAMMAI ENGINEERING COLLEGE

Chemical Engineering 412

Molten Salt Reactor system

MOLTEN-SALT REACTORS-HISTORY, STATUS, AND POTENTIAL

Overview of IAEA Activities in Support of Fast Reactors Development and Deployment & Objectives of this Meeting

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona USA

Recent Research Activities on Thorium and MSR in Japan

Molten Salt Converter Reactors: DMSR to SmAHTR and Back

GENERATION IV NUCLEAR ENERGY SYSTEMS

Method Excitation signal applied Wave response based on method Linear Differential pulse Square wave Cyclic Developed current recorded

Fusion-Fission Hybrid Systems

The Nuclear Fuel Cycle Lecture 5

Status of SMR Designs and their associated Fuel Cycle for Immediate-, Near-, and Long-term Deployment

Advanced Reactors and Long Term Prospects in Asia Pacific Region. Dr Adi Paterson ANA 2015 Conference, Sydney 2015.

TOO GOOD TO LEAVE ON THE SHELF

ATOMS FOR PEACE THE NEXT GENERATION. Dr. John E. Kelly U.S. Department of Energy, Office of Nuclear Energy September 29, 2016

FLOW & HEAT TRANSFER IN A PACKED BED - TRANSIENT

Chemical Engineering 412

Actinides/lanthanides separation in molten salt media: application to the liquid fuel reprocessing of molten salt fast reactor (MSFR)

Types of Nuclear Reactors. Dr. GUVEN Professor of Aerospace Engineering Nuclear Science and Technology Engineer

Molten-Salt-Reactor Technology Gaps

Energy From Thorium Foundation

Nuclear Power Plants

EM 2 : A Compact Gas-Cooled Fast Reactor for the 21 st Century. Climate Change and the Role of Nuclear Energy

Transcription:

Team 16: The Nuclear Family EN-FISSIONING A SUSTAINABLE FUTURE

Outline 2 Systems Designs Power Cycle Economics Conclusion Questions https://inlportal.inl.gov/portal/server.pt?open=514&objid=1269&mode=2&f eaturestory=da_553053

PROJECT OVERVIEW 3

Team Members 4 Thane Symens Mechanical Joel Smith Mechanical Meredy Brichford Chemical Christina Headley Chemical

Objective 5 Design Nuclear fission reactor Thorium fuel cycle Economic Analysis Customers: Electric power companies Problems to address 1. Environmental implications 2. Cost 3. Human health and safety 4. Efficiency 5. Availability

Design Approach 6 http://www.nrc.gov

REACTOR DESIGN 7

Nuclear Fission 8 http://www.atomicarchive.com

Nuclear s 9 http://www.met.reading.ac.uk

Thorium Cycle 10 Fission Th-232 Neutron Capture U-233 Th-233 β-decay Pa-233 β-decay http://www.energyfromthorium.com

Nuclear 11 s Control rods Coolant Containment http://www.bbc.co.uk

Type Selection 12 Molten Salt Breeder (MSBR) Fluid fuel Molten salt coolant Salt plug Oak Ridge National Laboratory (ORNL) test reactor http://www.ornl.gov

Design 13 Materials Core Control Rods Circulation Pump Safety systems Salt circulation pump Heat Exchanger Reflector Moderator Elements Fission Reactions Reflector Heat Exchanger Salt Plug

14 FUEL REPROCESSING DESIGN

15 Objective Remove feed poisons and fission products from fuel Why Reprocess? Maintain reactor performance Decrease stock pile of fuel Continuous operation

Fluorination 16 Main Components Uranium Thorium Waste Products Fluorinator Chemistry 2UF 4 + F 2 2UF 5 2UF 5 + F 2 2UF 6

Fluorination 17 Main Components Uranium Thorium Waste Products Fluorinator Chemistry 2UF 4 + F 2 2UF 5 2UF 5 + F 2 2UF 6

Fluorination 18 Main Components Uranium Thorium Waste Products Fluorinator Chemistry 2UF 4 + F 2 2UF 5 2UF 5 + F 2 2UF 6

Extraction 19 Main Components Uranium Thorium Waste Products Bismuth Extractor Chemistry UF4(salt)+4Li(Bi) 4 LiF(salt) + U(Bi) PaF4(salt)+4Li(Bi) 4 LiF(salt) +Pa(Bi)

Extraction 20 Main Components Uranium Thorium Waste Products Bismuth Extractor Chemistry UF4(salt)+4Li(Bi) 4 LiF(salt) + U(Bi) PaF4(salt)+4Li(Bi) 4 LiF(salt) +Pa(Bi)

Waste Product Removal 21 Main Components Thorium Waste Products Bismuth Back to Waste Products Rare earths Alkaline earths Alkali metals

Waste Product Removal 22 Main Components Thorium Waste Products Bismuth Back to Waste Products Rare earths Alkaline earths Alkali metals

Conclusion 23 Remove Uranium Waste Products Add to salt Uranium Return salt to reactor

POWER CYCLE DESIGN 24

Thermal System 25 https://energy.sdsu.edu/testhome/test/intro/exopengascyclep.html

Turbine 26 http://www.alstom.com/products-services/product-catalogue/power-generation/gaspower/gas-turbines/gt24-gt26-gas-turbines/ http://en.wikipedia.org/wiki/wind_turbine

Compressor 27 http://www.hansenwholesale.com/ceilingfans/ minkaaire/model.asp?prodno=f300-bn http://www.zetec.com/2010/06/blade-scanner/ http://www.huffingtonpost.com/2013/06/13/lung-transplantcystic-fibrosis_n_3437991.html

Heat Exchanger 28 http://www.explainthatstuff.com/how-heat-exchangers-work.html

Thermal System Design 29 Supercritical CO 2 Recompression Cycle Alternatives Steam Helium Efficiency Materials issues

Flownex Optimization 30 Pressure changes Pipe losses Component sizing Startup and shutdown simulation

Optimized System 31 Parameter Value Power Production 200 MWe Thermal Efficiency 44%

ECONOMIC ANALYSIS 32

33 Origins Characteristics of design High capital cost Low fuel cost Long lifetime

Economic Analysis 34 System Capital Costs Operation & Maintenance Costs Overall Annual Cost Thermal Loop $100 million $40 million $140 million Loop $33 million $60 million $93 million Total Annual Cost Cost of Electricity $2 million $1 million $3 million $236 million 15.8 /kw-hr

CONCLUSION 35

Lessons Learned 36 Teammate communication Escalation of project complexity Importance of accepting help Necessity of experimental data http://www.fujielectric.com

Acknowledgements 37 Prof. VanAntwerp, Calvin Faculty Advisor Sigval Berg, Industrial Consultant Stephen Theron, Flownex Bob DeKraker, Calvin College John Kutsch, Thorium Energy Alliance Prof. Heun, Calvin College Profs. Skutnik and Chvala, University of Tennessee

38 QUESTIONS http://www.theenergycollective.com

2024 © businessdocbox.com Privacy Policy | Terms of Service | Feedback