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RESEARCH AND DEVELOPMENT PROGRAMS, PATENTS AND LICENSES
11
11.1 Research and Development
In parallel, the Basic Design of the version adapted to EDF’s domestic requirements
for fleet replacement (the “EPR NM” version) continued in partnership with EDF.
AREVA NP has particular responsibility for the design of the nuclear steam
supply system and of the safety instrumentation and control system. This version
incorporates certain simplifications (single containment, etc.) in order to reduce
capital costs.
ATMEA1 REACTOR
The ATMEA1 reactor is being developed within the framework of the ATMEA joint
venture created in 2007 with Mitsubishi Heavy Industries (MHI). This 1100 MWe
pressurized water reactor (PWR) combines the know-how of both companies. It
is designed for medium capacity power grids. Following validation of the reactor’s
design basis in 2012 by the French nuclear safety authority ASN, the joint detailed
generic design was completed by the two companies, providing a model ready for
construction, depending on implementation prospects (see Sinop site in Turkey).
GENERATION IV SODIUM-COOLED FAST REACTORS (SFR)
To support sustainable development and the international initiative on Generation IV
reactors, AREVA continued its cooperation with the CEA on conceptual designs of
the nuclear island of Astrid (Advanced Sodium Technological Reactor for Industrial
Demonstration), the Generation IV demonstration reactor. This is a sodium-cooled
fast reactor (SFR) that will be used for technology and industrial demonstrations.
The front-end engineering and design of the Astrid reactor was finished in late
2015 with the submittal of the Preliminary Design Report and the Nuclear Safety
Design Basis document. Under the agreement between France and Japan on the
development of the sodium-cooled fast reactor technology and the Astrid reactor,
AREVA, as a French industrial company, is a stakeholder in the implementation
agreement signed between JAEA, the CEA, AREVA, Mitsubishi Heavy Industries
(MHI) and the latter’s subsidiary MFBR. The basic design of Astrid, to be carried
out over the 2016-2019 period, was kicked off in early 2016 with a milestone of
design basis validation by the end of 2017.
OTHER REACTOR CONCEPTS: SMR, HTR, MSR…
AREVA NP was selected by NuScale Power as part of its 50-MWe modular reactor
project funded by the DOE to carry out a certain number of studies and tests in
AREVA NP’s technical centers and to design and supply the fuel for this reactor. In
France, AREVA NP, alongside AREVA TA, is a member of the EDF-led consortium
to respond to the invitation to tender from the UK government related to conceptual
designs for small and modular reactors (SMR) with the perspective of being a
supplier of “technology building blocks” (components, instrumentation and control
system, fuel, etc.).
Concerning high-temperature reactors (HTR), AREVA NP is validating its expertise
and experience with this type of reactor by participating in the US Department of
Energy’s Next Generation Nuclear Plant (NGNP) project. The goal of that project is
to design a commercial high-temperature reactor to be used for the co-generation
of electricity and industrial process heat. AREVA also continues to follow through
with its commitments with regard to European HTR projects.
In addition, AREVA NP is actively monitoring other Generation IV reactor concepts
by participating in international collaboration projects such as the European Samofar
project for molten salt reactors and collaborating with the CNRS and the CEA
(NEEDS program).
ITER AND FUSION
As part of a contract with the ITER organization, AREVA NP is building a prototype
module of the primary wall of ITER, a highly complex component equipped with
beryllium tiles located near the plasma and thus subject to intense thermal flux.
AREVA NP is also participating in the activities of the Fusion Industry Innovation
Forum, whose prime objective is to define the technology roadmap leading to the
construction of the first power-generating fusion facilities.
Improving fuel and reactor design tools
AREVA NP puts considerable effort into improving its modeling tools and design
codes, both on its own and in collaborationwith theCEA. These projects prioritize the
development of advanced physical models that make use of expanding computer
modeling capabilities. They cover the state of the art of knowledge on PWR and
BWR extended validity ranges, architectures for modular applications, and graphical
interface ergonomics. Such evolutions help to improve the accuracy of code-based
predictions, reduce assembly and reload design costs, and improve design quality.
The goal of this research is to design and validate fuels and reactors that deliver
even better performance. Within this framework, the Arcadia neutronics calculation
software certified by the NRC is now in industrial use, in particular to support the
calculation of fuel reload supplies in the United States, with significant gains for the
operator in the number of assemblies to be supplied due to its enhanced ability to
accurately predict requirements compared with previous systems.
Increasing the competitiveness of our products and methods
and matching them to power plant operator requirements
AREVA NP continues to improve its products and services for operators of all
types of nuclear power plants (PWR, BWR, VVER and Candu), particularly in the
following areas:
p
safety instrumentation and control systems (TELEPERM
®
XS), measurement
and diagnostics products, safety-related sensors and emergency electrical
systems, preparation of advanced generations matched to the requirements
of new reactor projects;
p
services to operators to extend operating periods: diagnostics and demonstration
of the service period of components and structures; component maintenance
and replacement; and techniques to increase the resistance of components
to external events or for in situ repair, such as the cavitation peening process
successfully implemented in the United States: the line of related products is
presented to the utilities in the
Forward Alliance
catalogue;
p
safety reviews (10-year reviews, supplementary safety assessments) and products
to improve nuclear safety (complete range of containment filters for all types of
reactors; hydrogen risk management; reassurance of core cooling and of used
fuel storage pool cooling; new leak-proof systems for primary coolant pump seals;
instrumentation and tools for situation management): the line of related products
is presented to the utilities in the
Safety Alliance
catalogue;
p
value creation for reactor operators: increased availability; maintenance
automation and efficiency; increased power or efficiency; flexibility and load
following; new products that give customers increased operational savings and
performance; and enhanced worker safety such as dose reduction: the line
of related products is presented to the utilities in the
Value Alliance
catalogue;
2016 AREVA
REFERENCE DOCUMENT
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