JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments

Petti, David A.; Smolik, G.R.; Simpson, Michael F.; Sharpe, J. P.; Anderl, R.A.; Fukada, Satoshi; Hatano, Yuji; Hara, Masanori; Oya, Yasuhisa; Terai, Takayuki; Sze, D.K.; Tanaka, Satoru

doi:10.1016/j.fusengdes.2005.08.101

Cited by 52 publications

(41 citation statements)

References 23 publications

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“…To use vanadium alloy for structure materials and water or helium coolant has a problem from the viewpoint of compatibility [5]. A key issue associated with the use of Flibe is the control of tritium permeation and structure material corrosion, technologies for coating as tritium permeation barrier and reduction of impurities in the coolant or anti-corrosion coating would be required to solve the issue [6,7]. The development of materials and technologies to solve the compatibility and tritium permeation problems would be important for realization of the proposal blanket concept.…”

Section: Resultsmentioning

confidence: 99%

An optimization study of structure materials, coolant and tritium breeding materials for nuclear fusion-fission hybrid reactor

Ishibashi

Fujimoto

Matsumoto

2014

Progress in Nuclear Science and Technology

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The blanket materials were evaluated and optimized for use in a nuclear fusion-fission hybrid reactor by calculating the tritium breeding ratio (TBR), the ratio of thermal power output to fusion power input (Q value) and the temperature distributions. The calculation of TBR and Q value was performed by Monte Carlo code (MCNP-4C) and the temperature distributions by one dimensional heat equation. First, the structure materials, coolant and tritium breeding materials were investigated in terms of the TBR and the Q value. Secondly, the layer structure was optimized by calculating the temperature distributions in the blanket where the materials were selected by considering the former results of the TBR and Q value. As a result, the highest TBR and Q value could be obtained, if vanadium alloy structure material, helium gas coolant and molten salt tritium breeding material would be used as the blanket material. In addition, by optimizing the blanket structure using these materials, it would be possible to get a high TBR of 2.0 maintaining the temperature limit of the blanket materials, and about twenty times the thermal power output could be produced compared to the fusion power input under the condition of effective multiplication factor of 0.80.

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Section: Resultsmentioning

confidence: 99%

An optimization study of structure materials, coolant and tritium breeding materials for nuclear fusion-fission hybrid reactor

Ishibashi

Fujimoto

Matsumoto

2014

Progress in Nuclear Science and Technology

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“…There is no appreciable thermodynamic driver for corrosion of the alloys by molten fluorides to any significant extent. Therefore, pure molten fluoride salts will not react with the components of containment alloys [Grimes 1967, Sridharan et al 2008, Haubenreich and Engel 1970, Kondo et al 2009a, Kondo et al 2009b, Petti et al 2006, Baes 1974]. The principles and mechanisms pertinent to fluoride salts are analogous to some degree for chloride salts.…”

Section: Corrosion By the Molten Saltmentioning

confidence: 99%

“…With very low levels of contaminants in molten salts, corrosion by contaminants will be selflimiting, ceasing when the impurities have been expended or the solubility limits of the transition metal fluorides in the molten salt are reached. However, persistent sustained corrosion is possible if oxidants such as water or oxides are continuously replenished by leakage into the system, or if a component of the system is also an oxidant [Ozeryanaya 1985, Sridharan et al 2008, Haubenreich and Engel 1970, Kondo et al 2009a, Kondo et al 2009b, Petti et al 2006, Williams et al 2003]. …”

Section: Corrosion By the Molten Saltmentioning

confidence: 99%

“…Residual water in the salts can hydrolyze the salts at elevated temperatures, forming HF or HCl and the corresponding oxide. HF or HCl thus produced will react with active metals such as Cr, causing corrosion [Terai et al 2001, Nishimura et al 2001, Kondo et al 2009a, Petti et al 2006, Lovering and Gale 1983, Ozeryanaya 1985. In the case of FLiBe, the hydrolysis and corrosion reactions proceed by: where d denotes the dissolved state, and s denotes the solid state.…”

Section: Corrosion By the Molten Saltmentioning

confidence: 99%

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Engineering Database of Liquid Salt Thermophysical

Sohal¹,

Ebner²,

Sabhar³

2013

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The purpose of this report is to provide a review of thermophysical properties and thermochemical characteristics of candidate molten salt coolants, which may be used as a primary coolant within a nuclear reactor or heat transport medium from the Very High Temperature Reactor (VHTR) to a processing plant; for example, a hydrogen-production plant. Thermodynamic properties of four types of molten salts, including LiF-BeF 2 (67 and 33 mol%, respectively; also known as FLiBe), LiF-NaF-KF (46.5, 11.5, and 52 mol%, also known as FLiNaK), and KCl-MgCl 2 (67 and 33 mol%), and sodium nitrate-sodium nitrite-potassium nitrate (NaNO 3 -NaNO 2 -KNO 3 , 7-49-44 mol%, also known as Hitec® salt) have been investigated. Limitations of existing correlations to predict density, viscosity, specific heat capacity, surface tension, and thermal conductivity were identified. The impact of thermodynamic properties on the heat transfer, especially the Nusselt number, was also discussed.Stability of the molten salts with structural alloys and their compatibility with the structural alloys was studied. Nickel and high temperature alloys with dense Ni coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Of the chromium containing alloys, Hastelloy N appears to have the best corrosion resistance in fluorides, while Haynes 230 was the most resistant in chloride. In general, alloys with increasing carbon and chromium content are increasingly subject to corrosion by the fluoride salts FLiBe and FLiNaK due to attack and dissolution of the intergranular chromium carbide. Future research to obtain needed information was identified.

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“…Metallic beryllium contact has been shown to effectively reduce tritium fluoride in FLiBe. 34 Providing excess beryllium in the salt has been estimated to enable keeping the FLiBe tritium fluoride concentration below 20 ppt. 35 Tritium fluoride can also be decomposed by electrolyzing the melt at lower voltage than would be necessary to decompose the salt (either FLiBe or KF-ZrF 4 ).…”

Section: Temperature (°C)mentioning

confidence: 99%