Molten-salt reactors: new possibilities, problems and solutions

Ignatiev, V.; Feynberg, O.; Загнитько, А. В.; Merzlyakov, A. V.; Surenkov, A. I.; Panov, Alexander; Subbotin, V. G.; Афоничкин, В. К.; Хохлов, В. А.; Kormilitsyn, M. V.

doi:10.1007/s10512-012-9537-2

Cited by 79 publications

(19 citation statements)

References 2 publications

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“…A review of the latest reports [8][9][10][11][12][13][14][15] indicates this. The main cause is much the same as the one that caused the cancellation of the original project at Oak ridge.…”

Section: Review Of Present-day Research: the Problem Of Many Choicesmentioning

confidence: 99%

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Nuclear power can be the answer

Boothroyd¹

2017

Int. J. EQ

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This paper reviews the development of fast molten salt nuclear reactors (MSRs) to close the nuclear fuel cycle by processing future and existing nuclear waste so that it can be returned safely to the environment. It follows two earlier papers outlining the overall use of a range of MSR types and an outline of future proposed marketing of a universal modular thermal MSR design for general purposes. It is suggested that the future MSR industry will probably evolve into three major competitive global corporations. The first one, serving the Far East, seems likely to become entirely MSR based, whereas the other two serving Europe/Western Russia and the Americas may use the alternative lead-cooled fast reactor for waste disposal, which is the closest competitor to the MSR system. Although construction of full-scale fast (MSR) reactors for closing the fuel cycle may not eventuate until some years into the future, it is concluded that this need not delay the introduction of the general purpose thermal MSR reactor envisaged earlier. This new nuclear technology is considered essential to maintain base-load electricity in a world where agricultural needs are expected to take precedence over space requirements for wind and solar farms. Using Thorium, in addition to Uranium, nuclear fuel is sufficient for the next 1000 years. Thus this energy resource can be considered pseudo-sustainable and give us the time to restore our world to a state of balance and true sustainability. Attention is also drawn to the present dangers of continuing to increase the storage of nuclear waste and the refurbishing of old-design nuclear plant, which are already 40 years old.

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“…A review of the latest reports [8][9][10][11][12][13][14][15] indicates this. The main cause is much the same as the one that caused the cancellation of the original project at Oak ridge.…”

Section: Review Of Present-day Research: the Problem Of Many Choicesmentioning

confidence: 99%

“…The European EVOL reactor [6,8] is one such example as is the Russian MOSART study [12] designed specifically to burn up LWR/unwanted Plutonium waste as well as producing valuable materials by nuclear transmutation.…”

Section: Review Of Present-day Research: the Problem Of Many Choicesmentioning

confidence: 99%

Nuclear power can be the answer

Boothroyd¹

2017

Int. J. EQ

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“…New measurements of the physicochemical properties of fluoride salts have been performed in the framework of the MARS and the ISTC #3749 projects [17], the properties for a salt of LiF (78 mol%)-ThF 4 (22 mol%) are listed in Table 1. The third column summarizes the values used in these studies, at a mean temperature of 700°C (halfway between the low and the high operating temperatures).…”

Section: Data Used For the Simulations Of The Msfr 231 Physicochemimentioning

confidence: 99%

“…Abundances of seven delayed neutron precursors for two uranium isotopes. Numerical tools dedicated to neutronic and evolution calculations of the MSFR[17,21,26,[29][30][31][32][33][34][35][36][37][38][39][40][41][42][43][44]. Initial composition of the 233 U-started and TRU-started MSFR as provided by LPSC for the benchmark calculations and used in the following except in Sections 4.2.1 and 4.2.2.…”

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confidence: 99%

Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

Brovchenko

Kloosterman

Luzzi

et al. 2019

EPJ Nuclear Sci. Technol.

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This paper describes the neutronic benchmarks and the results obtained by the various participants of the FP7 project EVOL and the ROSATOM project MARS. The aim of the benchmarks was two-fold: first to verify and validate each of the code packages of the project partners, adapted for liquid-fueled reactors, and second to check the dependence of the core characteristics to nuclear data set for application on a molten salt fast reactor (MSFR). The MSFR operates with the thorium fuel cycle and can be started with 233U-enriched U and/or TRU elements as initial fissile load. All three compositions were covered by the present benchmark. The calculations have confirmed that the MSFR has very favorable characteristics not present in other Gen4 fast reactors, like strong negative temperature and void reactivity coefficients, a low-fissile inventory, a reduced long-lived waste production and its burning capacities of nuclear waste produced in currently operational reactors.

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“…The advanced metallic material for molten salt reactor (MSR) primary circuit will operate at temperatures up to 700-750°C [1][2][3][4]. The internal surface of the reactor vessel will be exposed to salt-containing fissile, fertile, fission product materials, and would receive a maximum fast and thermal neutron fluences up to 10 20 neutrons/cm 2 and 5 Â 10 21 neutrons/cm 2 , respectively [5].…”

Section: Introductionmentioning

confidence: 99%

Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF₂-UF₄ salt

Surenkov

Ignatiev

Presnyakov

et al. 2020

EPJ Nuclear Sci. Technol.

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Effect of the [U(IV)/U(III)] ratio of fuel salt on selective chromium corrosion and tellurium intergranular cracking (IGC) of Hastelloy N alloy in the LiF-BeF2-UF4 salt mixture was investigated. The chromium corrosion of Hastelloy N alloy is caused by the oxidation of chromium on the alloy surface by reaction with UF4. The tellurium IGC of Hastelloy N alloy is caused by the diffusion of tellurium along the grain boundaries with the formation of unstable tellurides with based metals and alloying additives. Results indicate that the selective chromium corrosion and the tellurium IGC of the Hastelloy N alloy in fuel salt can be controlled by the [U(IV)]/[U(III)] ratio. The tellurium IGC of Hastelloy N alloy exposed in fuel LiF-BeF2-UF4 salt can be avoided. For temperatures up to 760 °C the selective chromium corrosion can be minimized to the acceptable level when the [U(IV)]/[U(III)] ratio of fuel salt is bellow 30–40.

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Molten-salt reactors: new possibilities, problems and solutions

Cited by 79 publications

References 2 publications

Nuclear power can be the answer

Nuclear power can be the answer

Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF₂-UF₄ salt

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Molten-salt reactors: new possibilities, problems and solutions

Cited by 79 publications

References 2 publications

Nuclear power can be the answer

Nuclear power can be the answer

Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF2-UF4 salt

Contact Info

Product

Resources

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Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF₂-UF₄ salt