• Conceptual design studies
• Safety developments, in particular, to study the residual heat extraction; tests
with liquid salts have been undertaken to prove the ability of the cold plug
system to act as a security valve on the loop circuit
• Fabrication of the salt mixture (LiF-NaF-KF) to be used in the French molten
salt loop (FFFER project) has been achieved
• Experimental investigation of physicochemical properties of fluoride salts
• Experimental tests of the metallic-phase extraction process;
• Corrosion studies and experiments (this remains one of the main challenges for
the development of the reactor system)
Finally, it should be noted that the MSR with its Th cycle is one of the six
reference systems selected for R&D collaboration in the framework of the Generation IV International forum. The main contributors are the European partners,
supported by Russia as observer.
18.5 Conclusions
Since the early 1970s, studies and experimental projects have been undertaken in
Europe to examine the potential of Th-based fuels in a variety of reactor types.
These projects have all been successful from a scientific point of view, but not all
were followed up relative to the overall development of nuclear industry in Europe.
High-temperature reactors (HTRs), although very well suited for Th use, have not
been deployed to the benefit of LWRs. Results on the use of Th matrices in
Th-MOX fuels in LWRs are encouraging, but still need demonstration at a larger
scale in commercial conditions. Finally, the probably most efficient use of Th
would be in a salt, to feed MSRs. Conceptual studies and related experimental
programs are under way.
Open Access This chapter is distributed under the terms of the Creative Commons Attribution
Noncommercial License, which permits any noncommercial use, distribution, and reproduction in
any medium, provided the original author(s) and source are credited.
References
1. Lung M (1997) A present review of the thorium fuel cycle. EURATOM Report EUR 17771
2. Gruppelaar H, Shapira JP (2000) Thorium as a waste management option. In: 4th EURATOM
framework programme, EURATOM, EUR 19142 EN
3. Thorium cycle: development steps for PWR and ADS application. 5th EURATOM Framework
Programme Project, FIKI-CT-2000-00042
4. Verwerft M et al (2007) Oxide fuels: microstructure and composition variations (OMICO).
Final report EUR 23104, SCK•CEN, Mol
18 Overview of European Experience with Thorium Fuels
203
• Safety developments, in particular, to study the residual heat extraction; tests
with liquid salts have been undertaken to prove the ability of the cold plug
system to act as a security valve on the loop circuit
• Fabrication of the salt mixture (LiF-NaF-KF) to be used in the French molten
salt loop (FFFER project) has been achieved
• Experimental investigation of physicochemical properties of fluoride salts
• Experimental tests of the metallic-phase extraction process;
• Corrosion studies and experiments (this remains one of the main challenges for
the development of the reactor system)
Finally, it should be noted that the MSR with its Th cycle is one of the six
reference systems selected for R&D collaboration in the framework of the Generation IV International forum. The main contributors are the European partners,
supported by Russia as observer.
18.5 Conclusions
Since the early 1970s, studies and experimental projects have been undertaken in
Europe to examine the potential of Th-based fuels in a variety of reactor types.
These projects have all been successful from a scientific point of view, but not all
were followed up relative to the overall development of nuclear industry in Europe.
High-temperature reactors (HTRs), although very well suited for Th use, have not
been deployed to the benefit of LWRs. Results on the use of Th matrices in
Th-MOX fuels in LWRs are encouraging, but still need demonstration at a larger
scale in commercial conditions. Finally, the probably most efficient use of Th
would be in a salt, to feed MSRs. Conceptual studies and related experimental
programs are under way.
Open Access This chapter is distributed under the terms of the Creative Commons Attribution
Noncommercial License, which permits any noncommercial use, distribution, and reproduction in
any medium, provided the original author(s) and source are credited.
References
1. Lung M (1997) A present review of the thorium fuel cycle. EURATOM Report EUR 17771
2. Gruppelaar H, Shapira JP (2000) Thorium as a waste management option. In: 4th EURATOM
framework programme, EURATOM, EUR 19142 EN
3. Thorium cycle: development steps for PWR and ADS application. 5th EURATOM Framework
Programme Project, FIKI-CT-2000-00042
4. Verwerft M et al (2007) Oxide fuels: microstructure and composition variations (OMICO).
Final report EUR 23104, SCK•CEN, Mol
18 Overview of European Experience with Thorium Fuels
203