The Molten Salt Reactor (MSR) GIF System Development Progress Status - C. Renault (CEA/DEN/DER, France) C. Guérard (OECD/NEA)
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4TH INPRO-GIF INTERFACE MEETING
The Molten Salt Reactor (MSR)
GIF System
Development Progress Status
C. Renault (CEA/DEN/DER, France)
C. Guérard (OECD/NEA)
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 1
MSR potential and performances
A technology deeply investigated in the 60’s and 70’s
The successful operation of the
MSRE (Molten Salt Reactor
Experiment, ORNL-USA) from 1965
to 1969
3 fuel types:
• Uranium enriched to 30% in 235U
• Pure 233U Off-gas
• 239Pu Primary
System
Secondary
Salt Pump NaBF4 _ NaF Salt Pump
Coolant Salt
Fuel salt reprocessing was not implemented o
454 C
in MSRE, except the off-gas system
o o
Purified 704 C 621 C
Salt
Graphite
Moderator
The detailed design of a 1000 MWe Reactor
Heat
Exchanger
breeder reactor in Th/U cycle, the o
566 C
LiF _ BeF2 _ ThF4 _ UF4
MSBR (graphite moderated) Chemical 7
Processing Fuel Salt Steam Generator
Plant o
538 C
Freeze
Plug
Fuel salt Turbo-
71%LiF-16%BeF2-12%ThF4-0.3%UF4 Generator
Critically Safe, Passively Cooled Dump Tanks
(Emergency Cooling and Shutdown)
The termination of the program in 1975 left a number of open
questions relative to the viability of MSRs
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 2
MSR potential and performances
Two baseline concepts considered in GIF AHTR (Molten Salt cooled) with
superior economics
Fast neutron MSR (MSFR) as a long term
alternative to solid-fuelled fast neutron reactors
Graphite-free
core
• Attractive features (very negative feedback
coefficients, simplified fuel cycle with co-location of
reactor and reprocessing unit,…)
• Technological challenges need to be addressed Better compactness compared to
and the safety approach is to be established VHTR and passive safety potential
for medium to very high unit power
• Large commonalities in basic R&D areas (liquid salt technology, materials)
• Opportunities offered by liquid salts for heat transport in other systems (SFR, LFR, VHTR)
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 3
MSR potential and performances
MSFR for breeding and waste minimization
A single stream liquid fuel concept (no core structures)
Neutron spectrum: fast spectrum (thermal
MSFR 3000 MWt (~ 1350 MWe)
for MSBR)
Power density: 333 MWt/m3 (22 MWt/m3 for
Pool-type concept with high degree of
MSBR)
compactness (5 m diameter vessel)
Power conversion efficiency: > 45%
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 4
Status of MSR System in Gen IV
R&D Projects
Fast neutron MSR (MSFR) (Europe, Russia) and the AHTR (USA)
1. SI&A
Leader CEA (France)
2. Liquid salt chemistry and properties
Leader JRC/ITU (Euratom)
3. Materials and Components
Leader ORNL (USA) and KI (Russia)
4. System design and operation
Leader CNRS (France) and ORNL (USA)
5. Safety and safety system
Leader FzK (Europe) and ORNL (USA)
6. Fuel and Fuel cycle
Leader CNRS (France)
draft SRP April 2008 (V2.0)
• Materials and components selected as the first priority project
Towards a MoU (Memorandum of Understanding)
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 5
MSR R&D in Europe and elsewhere
From MOST to EVOL
A continuous and coordinated activity (European network) since 2001
2001-2003 from
MOST Confirmation of MSR potential 6 countries
+ Euratom MSBR
Identification of key issues (vs MSBR)
2004-2006
7 countries
LICORN Strenghthening of European network + Euratom
Follow-up of R&D progress + Russia
2007-2008 7 countries
ALISIA Review of liquid salts for various applications + Euratom
Preparation of European MSR roadmap + Russia
2009 8 countries
SUMO Feasibility demonstration of MSFR + Euratom
+ Russia
2009-2012 7 countries
… to
EVOL Optimization of MSFR + Euratom
MSFR
(remaining weakpoints) (+ Russia)
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 6
MSR R&D in Europe and elsewhere
A joint Euratom-Rosatom project in the 7th Euratom FWP
(EVOL+MARS)
Evaluation and Viability of Liquid Fuel Fast Reactor System
WP1
CNRS‐France CNRS‐France
Management & coordination
INOPRO‐France
WP2 FZD‐Germany
WP5
KIT‐G‐Germany
Pre‐conceptual Design Training, management of knowledge CNRS‐France
& Safety POLITO‐Italy UOXF‐DJ
and scientific dissemination
TUD‐The Netherlands
EVM‐Czech Rep.
BME‐Hungary
The support of Russian expertise
and existing facilities
WP3 CNRS‐France
Fuel salt chemistry ITU‐European Union ‐ Actinides (PuF3) solubilities
& reprocessing UOXF‐United Kingdom ‐ Molten salt properties
WP4 CNRS‐France Corrosion tests of NiWCr alloys
Structural materials A&D France in Russian convective loops
Euratom Consortium (EVOL) Rosatom (MARS)
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 7Summary and Conclusions
1. MSR has been recognized as a long term alternative to solid-fuelled
fast neutron systems with unique potential. This is a very distinctive
system to be analyzed very specifically (fuel cycle, safety, PR&PP).
2. The attention is focused today on fast spectrum concepts (MSFR)
for which attractive core designs have been developed for breeding
and MA burning. MSFRs combine BR>1 with strongly negative
“void” reactivity, which is unique among fast spectrum reactors.
3. Physico-chemical aspects on the MSR viability must be properly
addressed (reactor and clean-up unit). This is a key R&D area.
4. A European network on MSR R&D has been active since 2001 (5th
and 6th FWP). A new project has been submitted April 2009 as a joint
Euratom-Rosatom initiative (EVOL-MARS) and accepted
5. MARS and ISTC-3749 (started Feb 2009) projects take advantage
from the high potential of existing facilities in Russia.
6. The European/Russian and US interests are focused on different
concepts (MSFR, AHTR) but large commonalities exist in basic R&D
areas GIF framework has proved useful to optimize R&D effort.
4th INPRO-GIF Interface Meeting, Vienna, March 1-3, 2010 8You can also read
