Current State of Research in the Field of Detritiation of Technological Water Flows: A Review

Магомедбеков, Э. П.; Rastunova, I. L.; Кулов, Н. Н.

doi:10.1134/s0040579521060051

Cited by 8 publications

(2 citation statements)

References 60 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…From an environmental viewpoint, the treatment of tritiated water discharged from nuclear power plants is an urgent task not only in Fukushima but also across the world because it accounts for a major fraction of nuclear waste. − Tritium is radioactive and vigorously involved in metabolism, consequently careful consideration is required for health and safety risks . Most recently, a novel tritiated water separation method using hydrate was proposed.…”

Section: Introductionmentioning

confidence: 99%

Crystal Growth of Clathrate Hydrate Formed with Carbon Dioxide and Deuterium Oxide: Implications for Hydrate-based Tritium Separation

Maruyama,

Dogi,

Ohmura

2024

Energy Fuels

View full text Add to dashboard Cite

Tritium separation technology is a key method for treating contaminated water from nuclear power plants. Recently, a novel tritium separation method using deuterium oxide (D 2 O)based clathrate hydrate has attracted attention because it can reduce the tritium concentration in contaminated water from 4.77 × 10 5 Bq/kg to 1.55 × 10 3 Bq/kg. In this hydrate-based tritium separation method, tritium is concentrated on the surface of a D 2 O-based hydrate substrate. The mechanistic characteristics and formation kinetics of D 2 O-based hydrates need to be clarified to develop an efficient process for substrate formation. This study contributes to the process design by revealing the crystal growth of the CO 2 + D 2 O hydrate. The crystal growth behavior of the hydrate formed in the CO 2 + D 2 O system was experimentally observed under different subcooling temperatures (ΔT sub ) at 3.0 MPa. At all ΔT sub , hydrate crystals were formed at the gas−liquid interface and extended along the interface. After the interface was covered, hydrate crystals grew in the liquid phase. The variation in the morphology of CO 2 + D 2 O hydrate depended on ΔT sub . At ΔT sub = 1.6 K, polygonal crystals with side lengths of 0.2−0.6 mm were formed. At ΔT sub = 2.7 K, columnar crystals with a length of 1−2 mm were formed. At ΔT sub ≥ 3.3 K, dendritic crystals were formed. With an increase in ΔT sub , the size of the dendritic branches increased. The crystal growth dynamics and morphological tendency of the CO 2 + D 2 O hydrate were comparable to those of the CO 2 + H 2 O hydrate at fixed ΔT sub . Detailed theoretical discussions on the obtained results of surface kinetics, mass transfer, and heat transfer during hydrate formation from H 2 O and D 2 O were provided, considering the chemical potential, viscosity, and heat transfer of the liquids.

show abstract

Section: Introductionmentioning

confidence: 99%

Crystal Growth of Clathrate Hydrate Formed with Carbon Dioxide and Deuterium Oxide: Implications for Hydrate-based Tritium Separation

Maruyama,

Dogi,

Ohmura

2024

Energy Fuels

View full text Add to dashboard Cite

show abstract

“…These technologies will also be used in water detritiation systems for the International Thermonuclear Experimental Reactor (ITER) reactor. Water electrolyzers act as the bottom flow circulation unit in isotope separation plants in the water-hydrogen systems based on the Combined Electrolysis and Catalytic Exchange (CECE) process [1,2]. Recently, the possibility of using an electrochemical hydrogen pump (EHP) in the fuel cycle circuit for extracting, purifying and compressing hydrogen (including all isotopes) in the gas phase has also been growing in popularity [3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Features of Electrochemical Hydrogen Pump Based on Irradiated Proton Exchange Membrane

Ivanova,

Ivanov,

Mensharapov

et al. 2023

Membranes

View full text Add to dashboard Cite

An electrochemical hydrogen pump (EHP) with a proton exchange membrane (PEM) used as part of fusion cycle systems successfully combines the processes of hydrogen extraction, purification and compression in a single device. This work comprises a novel study of the effect of ionizing radiation on the properties of the PEM as part of the EHP. Radiation exposure leads to nonspecific degradation of membranes, changes in their structure, and destruction of side and matrix chains. The findings from this work reveal that the replacement of sulfate groups in the membrane structure with carboxyl and hydrophilic groups leads to a decrease in conductivity from 0.115 to 0.103 S cm−1, which is reflected in halving the device performance at a temperature of 30 °C. The shift of the ionomer peak of small-angle X-ray scattering curves from 3.1 to 4.4 nm and the absence of changes in the water uptake suggested structural changes in the PEM after the irradiation. Increasing the EHP operating temperature minimized the effect of membrane irradiation on the pump performance, but enhanced membrane drying at low pressure and 50 °C, which caused a current density drop from 0.52 to 0.32 A·cm−2 at 0.5 V.

show abstract

Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station

Xu,

Lv,

et al. 2024

Annals of Nuclear Energy

View full text Add to dashboard Cite

Current State of Research in the Field of Detritiation of Technological Water Flows: A Review

Cited by 8 publications

References 60 publications

Crystal Growth of Clathrate Hydrate Formed with Carbon Dioxide and Deuterium Oxide: Implications for Hydrate-based Tritium Separation

Crystal Growth of Clathrate Hydrate Formed with Carbon Dioxide and Deuterium Oxide: Implications for Hydrate-based Tritium Separation

Features of Electrochemical Hydrogen Pump Based on Irradiated Proton Exchange Membrane

Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station

Contact Info

Product

Resources

About