Nuclear waste transmutation performance assessment of an accelerator driven subcritical reactor for waste transmutation (ADS-NWT)

Chen, Zhong; Wu, Yican; Yuan, Bin; Pan, Dongmei

doi:10.1016/j.anucene.2014.09.002

Cited by 20 publications

(7 citation statements)

References 10 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Reprocessing spent nuclear fuel (SNF) is a high-tech process with the purpose of minimizing the radiation hazard of this fuel, ensuring the safe disposal of unused components, and facilitating the release of useful substances (primarily uranium and plutonium). At the same time, to ensure economic efficiency and improve environmental safety, the issue of the minor actinides (MA) arises [ 1 , 2 , 3 , 4 , 5 ]. The MA, which are long-lived radioactive isotopes of americium, curium and neptunium, all transuranic chemical elements, are primary contributors to the high radioactivity of the waste remaining after SNF processing.…”

Section: Introductionmentioning

confidence: 99%

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

et al. 2021

View full text Add to dashboard Cite

The NdF3 solubility in molten eutectic FLiNaK, which is a conceivable medium for a molten salt reactor (MSR), was determined by the quasi-binary phase diagram FLiNaK-NdF3. The eutectic mixture FLiNaK was prepared by direct melting of components LiF, NaF and KF·HF. The acidic anhydrous salt (KF·HF) was used instead of the hygroscopic KF. The NdF3 was sintered by hydrofluorination of Nd2O3. The oxygen impurity in the prepared eutectic FLiNaK, determined by an oxygen analyzer LECO OH836, was 0.036 wt.%, whereas the NdF3 contained 0.04 wt.% of oxygen. A part of the FLiNaK-NdF3 quasi-binary phase diagram was obtained using two thermal analysis techniques: differential thermal analysis (DTA) and differential scanning calorimetry (DSC). The FLiNaK-NdF3 phase diagram in the region of 0–30 mol.% NdF3 contains one eutectic at 2 mol.% NdF3 and 450 °C and two peritectic points: 8 mol.% NdF3 at 500 °C and 22 mol.% NdF3 at 575 °C. The region of the FLiNaK-NdF3 phase diagram below the liquidus line is rather complicated due to the complex structure of the multicomponent system in its molten state, as in its solid state. The NdF3 solubility in FLiNaK is about 5 mol.% at 490 °C and 29 mol.% at 700 °C; this means that the process of the MA transmutation in the MSR can be carried out in molten FLiNaK with a content of actinides as high as 15–20 mol.% in the temperature range of 550–650 °C.

show abstract

Section: Introductionmentioning

confidence: 99%

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

et al. 2021

View full text Add to dashboard Cite

show abstract

“…At that time they were not pushed forward though, mainly due to the lack of economic investment as a result of their complexities in comparison with other reactors proposed at that time, such as the light-water reactors: PWR (Pressurized Water Reactor) and BWR (Boiling Water Reactor). However, radioactive waste concerns involving light-water reactors in conjunction to greenhouse effects have contributed to put the ADS reactor back to the game [4][5][6][7][8][9].…”

Section: Introductionmentioning

confidence: 99%

On the calculation of neutron sources generating steady prescribed power distributions in subcritical systems using multigroup X,Y-geometry discrete ordinates models

Léonardo¹,

Moraes²,

Filho³

et al. 2021

Preprint

View full text Add to dashboard Cite

In this paper a methodology is described to estimate multigroup neutron source distributions which must be added into a subcritical system to drive it to a steady state prescribed power distribution. This work has been motivated by the principle of operation of the ADS (Accelerator Driven System) reactors, which have subcritical cores stabilized by the action of external sources. We use the energy multigroup two-dimensional neutron transport equation in the discrete ordinates formulation (S N ) and the equation which is adjoint to it, whose solution is interpreted here as a distribution measuring the importance of the angular flux of neutrons to a linear functional. These equations are correlated through a reciprocity relation, leading to a relationship between the interior sources of neutrons and the power produced by unit length of height of the domain. A coarse-mesh numerical method of the spectral nodal class, referred to as adjoint response matrix constant-nodal method, is applied to numerically solve the adjoint S N equations. Numerical experiments are performed to analyze the accuracy of the present methodology so as to illustrate its potential practical applications.

show abstract

“…Accelerator‐driven subcritical system, the most promising metamorphic technology in the industry, is considered by all countries to be the most reasonable and effective method to solve the problem of spent fuel . The lead‐bismuth eutectic alloy (LBE) is selected as spallation target material and coolant due to its good heat transfer capability and good neutronics performance .…”

Section: Introductionmentioning

confidence: 99%

Effect of current density on micro‐arc oxidation of Q235 steel and corrosion resistance in liquid Pb‐Bi

Zhu

Zhang

et al. 2019

Materials & Corrosion

View full text Add to dashboard Cite

An attempt has been made to improve the corrosion resistance in liquid Pb-Bi by micro-arc oxidation (MAO), and the effects under different current densities on the corrosion resistance of the coatings were discussed. Scanning electron microscope, energy dispersive spectrometer, and X-ray diffraction were used to analyze the surface morphology and phase constituents of the MAO coatings produced under different current densities. The corrosion resistance of the coatings was evaluated by studying the element changes and morphology evolution. The results show that the compactness of the ceramic coating decreases with the current density increasing. In contrast to the performance of matrix metal, the ceramic coating exhibited a much better corrosion resistance in liquid Pb-Bi. Moreover, the ceramic coating produced under current density of 10 A/dm 2 shows the best corrosion resistance. K E Y W O R D S current density, fusion-brazing, liquid Pb-Bi corrosion, micro-arc oxidation

show abstract

Nuclear waste transmutation performance assessment of an accelerator driven subcritical reactor for waste transmutation (ADS-NWT)

Cited by 20 publications

References 10 publications

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

On the calculation of neutron sources generating steady prescribed power distributions in subcritical systems using multigroup X,Y-geometry discrete ordinates models

Effect of current density on micro‐arc oxidation of Q235 steel and corrosion resistance in liquid Pb‐Bi

Contact Info

Product

Resources

About