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IAEA-UNIPI Training
Course on Natural Circulation Phenomena and Modelling
in Water Cooled Nuclear Power Plants
San Piero a Grado (Pisa), Italy
22 to
Organized by:
San Piero a Grado Nuclear Research Group (GRNSPG)
University of Pisa (UNIPI)
Via Livornese 1291
San Piero a Grado (Pisa), Italy
In cooperation with:
International Atomic Energy Agency (IAEA)
Department of Nuclear Energy
Wagramerstrasse 5
1400
DOWNLOAD HERE
THE BROCHURE OF THE COURSE
1. BACKGROUND
AND HISTORY
Nuclear power has proven its viability
in many IAEA Member States. Today the worldwide installed nuclear capacity is
approximately 370 GWe with nuclear power supplying 15% of the world’s
electricity.
Light water reactors and heavy
water reactors combined represent 94% of the global nuclear power
capacity, and advanced designs are being developed in several IAEA Member
States to help meet future energy needs. Common goals for advanced
designs are high reliability and competitive economics while meeting stringent safety
requirements. To assure competitive economics, design organizations are
challenged to develop advanced nuclear power plants with lower capital costs,
and sizes suitable for various grid capacities and owner investment
capabilities. This includes large sizes for some markets and small and
medium sizes for others.
To achieve the largest cost
reductions, both proven means and new approaches should be applied. Proven
means include streamlining construction methods to shorten the construction
period; design standardization; efficient project management and others. New approaches include: design for modularization,
factory fabrication, and series production; design simplification; design for
higher temperature (higher thermal efficiency); incorporation of passive
safety systems for cases where the safety function can be met at reduced cost;
and improvements in the technology base (e.g. more accurate data bases of
thermo-physical properties and thermo-hydraulic relationships, and improved
computer codes and code validation) to reduce the need to incorporate
excessively large margins into the design simply for the purpose of allowing
for limitations in analytical methodology and uncertain data.
Passive safety
systems based on natural circulation are key to several evolutionary water-cooled
designs and many innovative water-cooled reactor designs. Some designs also
utilize natural circulation to remove core heat during normal operation.
The IAEA fosters international
cooperation in examining natural circulation for removal of core heat under
normal operation and accident conditions, and to provide cooling of the
containment. Several organizations worldwide are collaborating in an IAEA
Coordinated Research Programme on “Natural Circulation Phenomena, Modelling and
Reliability of Passive Systems that Utilize Natural Circulation”. This activity
is building on other recent IAEA activities on passive safety systems,
thermo-hydraulic relationships and experimental tests and qualification of
analytical methods to address thermo-hydraulic phenomena, and valuable
information from research projects on natural circulation and passive system
reliability within the European Commission is being contributed.
This Course on Natural
Circulation Phenomena and Modelling in Water-Cooled Nuclear Power Plants
utilizes information, results and expertise shared through these various
activities, and especially the current IAEA Coordinated Research Programme on
“Natural Circulation Phenomena, Modelling and Reliability of Passive Systems
that Utilize Natural Circulation”.
The Course has been already
successfully organized in four occasions:
- in 2004 at the International
Centre for Theoretical Physics (ICTP),
- in 2007 at the International
Centre for Theoretical Physics (ICTP),
- in 2008 at the
- in 2008 at the International
Centre for Theoretical Physics (ICTP),
2. COURSE
OBJECTIVES
The objectives of the Course are to provide participants with
instruction on:
·
natural
circulation during reactor start-up and operation, methods of analyses and
governing equations, passive system initiation and operation, flow stability,
scaling laws for experiments;
·
phenomena
that influence natural circulation (e.g. behaviour in large pools of liquid,
effects of non-condensable gasses on condensation heat transfer; condensation
on containment structures, behaviour of containment emergency systems,
thermo-fluid dynamics and pressure drops in various configurations, steam-liquid
interaction, gravity driven cooling, liquid temperature stratification,
behaviour of emergency heat exchangers and isolation condensers, stratification
and mixing of boron);
·
experimental
databases for these phenomena;
·
methodology
for determining the reliability of passive systems that utilize natural
circulation.
The Course will conclude with
an exam and presentation of Certificates to the participants confirming
successful completion of the Course, if examination is taken.
Final
Agenda is available here
The Roadmap for the Course is shown below:
