The thorium molten salt reactor: Moving on from the MSBR

Mathieu, L.; Heuer, D.; Brissot, R.; Garzenne, C.; Brun, C. Le; Lecarpentier, David; Liatard, E.; Loiseaux, J.M.; Méplan, O.; Merle, E.; Nuttin, A.; Walle, E. van; Wilson, J. N.

doi:10.1016/j.pnucene.2006.07.005

Cited by 224 publications

(90 citation statements)

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“…In addition, several specimens, for TEM studies, were prepared as disks of 3 mm in diameter. Thin foils were obtained by mechanical thinning of the disks down to 100 µm, followed by twin-jet electropolishing, with an alcoholic solution of 5% HClO 4 .…”

Section: Materials and Experimental Proceduresmentioning

confidence: 99%

“…Therefore, the structural materials of MSR will be subjected to the extreme environments, i.e., high temperature, high neutron doses and corrosive coolant. 3,4) Thus, the development of the MSR much depends on the progress in developing such structural materials that should meet a number of special requirements: a high corrosion resistance to fluoride salt melts; sufficient radiation resistance; adequate high-temperature strength and good manufacturability (ability to be deformed, machined, welded, etc.). 5) Nickel-base NiMoCr alloy has high strength and excellent corrosion resistance at high temperature, wherein molybdenum and chromium were added respectively to strengthen and improve the oxidation resistance of alloy.…”

Section: Introductionmentioning

confidence: 99%

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Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

Huang

et al. 2014

Mater. Trans.

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A nickel-base high-temperature alloy (Ni-17Mo-7Cr) has been characterized by nanoindentation and transmission electron microscopy to determine the changes of nanoindentation hardness and microstructural evolution under ion irradiation. Ion irradiation experiments for bulk and thin-foil specimens of Ni-17Mo-7Cr alloy were carried out at room temperature, up to 6.6 dpa, by 7 MeV Xe 26+ and 1 MeV Xe 20+ ions, respectively. The continuous stiffness measurement (CSM) with a diamond Berkovich indent was used to measure the depth profile of hardness. Nanoindentation results for bulk specimens showed an evident ion irradiation induced hardening phenomenon, and the nanoindentation hardness increases with increasing ion dose. High number density of nano-scale black spots and linear-like defects were observed in thin-foil specimens irradiated at 0.33 and 6.6 dpa, respectively. High-resolution transmission electron microscopy images revealed that the black spots were nanoscale solute clusters and dislocation loops, while the linear-like defects were found to be Ni, Mo and Cr-enrichment regions by using the highangle annular dark field-scanning transmission electron microscope. The ion irradiation induced defects can be responsible for the hardening of Ni-17Mo-7Cr alloys.

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Section: Materials and Experimental Proceduresmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

Huang

et al. 2014

Mater. Trans.

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“…Overall, total US LMFBR R&D spending has been~150 times that devoted to MSR-related work. 10 "Two-fluid" rather than "two-salt" because most of ORNL's MSBR modeling work assumed that the reactor's fuel salt would contain thorium as well as fissile. Such systems are now generally called "1½ salt" reactors.…”

Section: Discussionmentioning

confidence: 99%

Why the molten salt fast reactor (MSFR) is the “best” Gen IV reactor

Siemer

2015

Energy Science & Engineering

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A simultaneously "nuclear", permanent, and in-time solution to mankind's energy-related problems would require the relatively rapid manufacture of 10,000-30,000 genuinely sustainable, full-sized (~1 GW e ) reactors. This "nuclear renaissance" would have to be implemented with breeder reactors because today's commercial nuclear fuel cycle is unsustainable and based upon a fuel ( 235 U) that is intrinsically expensive and politically problematic. The purpose of this paper is to point out why a simple/cheap "minimal reprocessing" implementation of the European Union's (EU's) molten salt fast reactor (MSFR) concept represents the most promising way to implement that technical fix:• It would be relatively simple/cheap to both build and operate, • Its fuel cycle is genuinely sustainable (no fuel shortages "forever"), • Radwaste management would also be relatively simple and cheap, • Operation would neither generate nor require huge amounts of transuranic (TRU) elements, • The consequences of accidents (fuel spills, etc.) would be relatively benign, • When steady state is achieved, the world would no longer need its uranium enrichment facilities.

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“…[22,23]; • 233 U-232 Th fuelled MSR with fluoride salt an fast neutron spectrum, promoted by the CNRS, ref. [21]; • 238 U-Pu fuelled MSR with chloride salt a fast neutron spectrum, ref.…”

Section: Molten Salt Reactors (Msr)mentioning

confidence: 99%

Nuclear energy generation, numerical simulation accuracy and nuclear data

Lecarpentier

2007

Nd2007

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Abstract. In the French context, it appears that the accuracy of the nuclear data comply with the utility need. However, a constant reduction of the calculation uncertainties is achieved with more precise physics and numerical methods and improved nuclear data. The aims for this uncertainty reduction are: to increase the competitiveness, by reduced operating conservatisms in order to extend the reactor lifespan and by optimising the existing series of nuclear plants and associated fuel cycle: extended burn-up, MOX fuel, reduced damage to the reactor vessel. . . and to evaluate and to develop the future nuclear energy systems (Generations III and IV) with a sufficient accuracy. The nuclear reactor operation is currently supported by numerical simulation: if the discrepancies between precalculated values and measures in operation are sufficiently low, the required authorisations are given by the Safety Authority. EDF core calculations have been relying on JEF2.2 for more than fifteen years. This association of code and database gives a satisfying uncertainty level for the current reactors and associated fuel management, but the development of a new calculation scheme named N3C-V2 has been decided at EDF, relying simultaneously on: -improved numerical scheme allowed by today's powerful computers and recent physics improvements; -a new set of nuclear data: JEFF3.1. This work is considerable, and the expected results are the reduction of uncertainty on the main parameters of future optimised fuel management in existing reactors and in EPR. Concerning Gen IV reactors and actinide transmutation, progresses are still needed (even for Sodium cooled FBR which are the reference Gen IV solution of the industrial EDF), mainly in the fast spectrum. The aim is to evaluate with a better accuracy: Fuel evolution, in particular, the formation of Minor Actinides (Am, Cm, Np) or important isotopes, like 232 U in the thorium cycle; Breeding gain ( 238 U and 232 Th captures, 239 Pu and 233 U fissions, in the fast range for 238 U and 239 Pu, in all ranges for 232 Th and 233 U); Doppler effect; Void effect in fast spectrum reactors is a major issue and can be influenced by the heavy nuclei cross sections, but also by the elastic and inelastic scattering cross sections of the coolant (scattering of Na or Pb for ex.). Finally, uncertainty on cross-sections must become available in the evaluation files, for they will help to differentiate the part of uncertainty coming from the data and from the calculation methods.

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The thorium molten salt reactor: Moving on from the MSBR

Cited by 224 publications

References 2 publications

Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

Nanostructure Variations and Their Effects on Mechanical Strength of Ni-17Mo-7Cr Alloy under Xenon Ion Irradiation

Why the molten salt fast reactor (MSFR) is the “best” Gen IV reactor

Nuclear energy generation, numerical simulation accuracy and nuclear data

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