tatjana jevremovic, nptds · pdf filecomputational fluid dynamics codes for design ......
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Technical Meeting to Examine the Techno-Economics of and
Opportunities for Non-Electric Applications of Small and Medium
Sized or Modular Reactors
22 – 24 May, 2017 VIC
Tatjana Jevremovic, NPTDS
OUTLINE
NPTDS WCR Team Activities
Nuclear Power: Status and
Prospective
Near/Long-Term Challenges and
Trends
OUTLINE
NPTDS WCR Team Activities
Nuclear Power: Status and
Prospective
Near/Long-Term Challenges and
Trends
• Fosters sustainable nuclear energy
development by supporting existing and new
nuclear programmes around the world
• Provides technical support on the nuclear fuel
cycle and the life cycle of nuclear facilities, and
builds indigenous capability in energy planning,
analysis, and nuclear information and knowledge
management
S
M
R
Fast Reactors
WCR
GCR
NEApp
Technology Development for Advanced Reactor Lines
NPTDS Sub-Programme Structure
MSR
WCR Technology Development Team Core Business
HWRs
SCWRs
Severe Accidents
RTA
E & T
Simulators
LWRs
Assist MSs with national nuclear
programmes;
Support innovations in nuclear power
deployment;
Facilitate and assist international
R&D collaborations.
Information Exchange
Modelling and
Simulations
Safety
Development of
Methodologies
Technology Support
Education and
Training
Knowledge
Preservation
OUTLINE
NPTDS WCR Team Activities
Nuclear Power: Status and
Prospective
Near/Long-Term Challenges and
Trends
NPP Status in the World: 449 in Operation
https://www.iaea.org/PRIS/WorldStatistics/OperationalReactorsByType.aspx
NPP Status in the World: 60 Under Construction
Under Construction Reactors
https://www.iaea.org/PRIS/WorldStatistics/OperationalReactorsByType.aspx
NPP Status in the World: 160 Shutdown
Permanent Shutdown
https://www.iaea.org/PRIS/WorldStatistics/OperationalReactorsByType.aspx
NPP Status in the World: New Connections to Grid
https://www.iaea.org/PRIS/WorldStatistics/OperationalReactorsByType.aspx
ARIS Data Base https://aris.iaea.org/
OUTLINE
NPTDS WCR Team Activities
Nuclear Power: Status and
Prospective
Near/Long-Term Challenges and
Trends
WCR Activities in 2017
• Coordinated Research Projects (CRPs) – 3 ongoing and 2 new 1. Computational Fluid Dynamics Codes for Design (2012-2018)
2. Prediction of Axial and Radial Creep in Pressure Tubes (2013-2017)
3. Thermal Hydraulics of SCWRs (2014-2018)
4. Probabilistic Safety Analysis [Benchmark] for Multi-unit, Multi-type NPP Sites (2017-2020)
5. Methodology for Developing Pipe Failure Rates for Advanced Water-cooled Reactors (2017-2020)
• International Collaborative Standard Problems (ICSPs) 1. Numerical Benchmark Database for PHWR Transients (2016-2019)
• Technical Meetings on New Concepts in Innovative Water Cooled Reactor Technology, 13 – 17 March
Developing a Systematic Education and Training Approach Using Personal Computer Based Simulators for Nuclear Power Programmes, 15 – 19 May
Workshop on Advances in Understanding the Progression of Severe Accidents in BWRs, 17 – 21 July
Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors, 9 – 12 October
• Consultancy Meetings Two meetings to develop proposals for two new CRPs: Presentation
Effective Utilization of THERPRO Data Base, 22 – 23 February
• Data Bases ARIS
THERPRO
• Training Courses on: Understanding Physics and Technology of WCRs through Simulators: 3 new courses
Reactor Technology Assessment (forthcoming Ghana)
Use of CFD in NPP Design, China
New Concepts in Innovative Water
Cooled Reactor Technology
13 – 17 March
19 participants from 16 Member States
Current & Near-term Mid-term
Drivers for Innovations?
Technical Meeting on New Concepts in Innovative Water
Cooled Reactor Technology, 13 – 17 March
1. Growth of Nuclear Power - Perspectives on Energy Demand
•Goal 7: Ensure access to affordable, reliable, sustainable and modern energy for all
•Goal 13: Take urgent action to combat climate change and its impacts
Average annual population growth
2050: 9 and 10 billion,
compared to the 7.6 billion
today
Relation between energy use
of the countries per capita and
gross domestic product (GDP)
Many factors are contributing the increased demand for global energy use. Global population growth is a strong driver for increased global energy needs.
Drivers for innovations: • New reactor types
• Cogeneration
• …
Technical Meeting on New Concepts in Innovative Water
Cooled Reactor Technology, 13 – 17 March
1. Growth of Nuclear Power - Perspectives on Energy Demand
•Goal 7: Ensure access to affordable, reliable, sustainable and modern energy for all
•Goal 13: Take urgent action to combat climate change and its impacts
Example about the interconnection
between atmospheric CO2 content
and global temperature change
during the historical time period
more than 100 years
Paris Convention on Climate Change set a goal
of limiting global warming to less than 2 °C
compared to pre-industrial levels.
The agreement calls for zero net anthropogenic
greenhouse gas emissions to be reached
during the second half of the 21st century. 2017: 392 GW(e)
15% total energy consumption Importance of
continuous
development of
NPP technology
highlighting
radically
innovative WCR
designs for
electric and non-
electric use
Technical Meeting on New Concepts in Innovative Water
Cooled Reactor Technology, 13 – 17 March
2. Non-Electrical Advanced Applications of WCRs
Non-electric applications for nuclear power:
• District heating
• Nuclear (CO2 free) desalination
• Process heat supply
• Ship propulsion
• Hydrogen production
• Coal gasification
• Other synthetic fuels
• Oil extraction
require high process
temperatures } limited market
Various markets and/or regulatory drivers What is needed to further nuclear desalination (150 reactor-years of experience):
Develop key attributes and a prototype or pilot programme plan for developing
licensing regulations and activities for coupling an approved nuclear plant design
(WCRs) with a desalination facility.
Perform an optimization of the steam cycle, system, and component design, for
prototype examples of the coupled facilities.
Develop a template for follow-on evaluations.
Perform a study to determine the range of desalination options and capacities to be
supported.
Identify options for alternative energy sources for the thermal portion of the
desalination facility when the nuclear facility is experiencing an outage.
700 reactor-years of experience
Technical Meeting on New Concepts in Innovative Water
Cooled Reactor Technology, 13 – 17 March
3. Drivers for WCR Design Innovations
Safety
Public Acceptance
Competitiveness
Simplicity
• Severe accidents and extreme external hazards
• Passive safety systems (only?)
• Small OR large reactor designs
• Robust and reliable cooling systems to remove residual
decay heat that can function for both DBA and BDBA
• Strengthen containment integrity by ensuring availability of
monitoring, cooling, and venting functions under severe
accident conditions
• Strengthen severe accident management guides (SAMGs)
• Robust capability to monitor key plant parameters
• Innovate fuel designs to improve safety of large and small
reactors (to reduce release of radioactive materials and
reduce spent fuel volumes)
• Boron free reactor designs
• Dramatic reduction of the EPZ (zero EPZ?!?)
• Resistance of large WCRs to extreme seismic events
• NPP underground (whole or partially; innovatively compact
designs; earthquake resistant designs?)
• Floating reactors (electricity, process heat, desalination)
• Renewables with innovative small & compact NPPs
• New construction methods / Licensing
Innovations: small – compact designs that
can replace retiring NPP and coal plants,
install in rural areas, flexible to adapt to non-
electric applications and integration with
renewables
Plug-in plug-out
New CRP on Probabilistic Safety Analysis (PSA)
for Multi-Unit, Multi-Reactor Sites
• At many nuclear sites world-wide, several NPPs,
either of the same or of different types, designs, or
age, are co-located on a single site.
• Regulations generally recognize the potential for
multiunit accidents, PSA of NPPs have mainly
focused on estimating the risk arising from damage
to a single NPP.
• Safety assessments based on deterministic and
probabilistic approaches in which the risk at a site with
multiple reactors can be represented by summing up
the risks of individual units.
• simplified approach with several limitations
ignores complex interactions during a severe
event impacting a multiunit site.
Fukushima accident lesson learned: Need to improve PSA
methodologies when applied to multi-unit, multi-reactor-
type nuclear sites.
Several methods are being explored around the world to extend
or “translate” per-unit PSA results to multi-unit site PSA results,
such as core damage and large release frequencies.
This CRP will bring together experts from LWR and PHWR MSs
to benchmark their practices, compare assumptions and
results and recommend improvements to the "Framework and
Process for Multi-unit Site PSA" (parallel NSNI Activity).
Example – Atucha, Argentina:
• 2 unique PHWRs operating
• 1 SMR under construction
• 1 CANDU planned
• 1 PWR possible
One NPP site with five
different reactor types
New CRP on METHODOLOGY FOR DEVELOPING PIPE
FAILURE RATES FOR
ADVANCED WATER-COOLED REACTORS
• Objectives: – Increase the knowledge and understanding of the methodology in MSs
on how to predict pipe failure rates for advanced WCRs that utilize the current state-of-knowledge regarding the five decades of extensive and well documented operating experience data on piping system components in WCRs
– Provide specific guidelines in consideration to the effect of new materials on piping reliability
– Develop common set of benchmarks
• 1st CM:
– February 27 – March 2, 2017
– 4 MSs and OECD participants developed a detailed proposal for
launching the CRP in 2018
Thank you!