scholarly journals Novel Non-Evaporable Getter Materials and Their Possible Use in Fusion Application for Tritium Recovery

Molecules ◽  
2020 ◽  
Vol 25 (23) ◽  
pp. 5675
Author(s):  
Alessia Santucci ◽  
Luca Farina ◽  
Silvano Tosti ◽  
Antonio Frattolillo
Keyword(s):  
Flow Rate ◽  
Nuclear Reactors ◽  
Lower Number ◽  
Lower Amount ◽  
Helium Flow ◽  
Primary Coolant ◽  
Purification System ◽  
Coolant Loop ◽  
Metallic Compounds ◽  
Gas Molecules

Non-evaporable getters (NEGs) are metallic compounds of the IV group, particularly titanium and/or zirconium-based alloys and are usually used as pumps in vacuum technologies since they are able to sorb, by chemical reactions, most of the active gas molecules, with particular efficacy towards hydrogen isotopes. This work suggests an alternative application of these materials to fusion nuclear reactors, where there is the need to recover small amount of tritium from the large helium flow rate composing the primary coolant loop. Starting from the tritium mass balance inside the primary coolant loop, the amount of coolant to be routed inside the coolant purification system (CPS) is identified. Then a feasibility study, based on the bulk getter theory, is presented by considering three different commercial alloys, named ST707, ST101 and ZAO. The results provide the mass, the area and the regeneration parameters of the three different alloys necessary to fulfill the requirements of the CPS unit. By comparing the features of the three alloys, the ZAO material appears the most promising for the proposed application because it requires the lower amount of material and a lower number of regeneration cycles.

Feasibility Assessment of Air-Cooling System As an Ultimate Heat Sink of the ATOM System

2018 ◽  
Author(s):  
Doyoung Shin ◽  
Gwang Hyeok Seo ◽  
Min Wook Na ◽  
Sung Joong Kim ◽  
Yonghee Kim ◽  
...  
Keyword(s):  
Flow Rate ◽  
Heat Sink ◽  
Cooling System ◽  
Air Cooling ◽  
Primary Coolant ◽  
Final Heat ◽  
Feasibility Assessment ◽  
Environment Temperature ◽  
Air Cooling System ◽  
Atom System

Nowadays Small Modular Reactors (SMRs) have been receiving considerable attentions worldwide for potential advantages of an excellent flexibility for siting, low capital investment, and advanced safety. In Korea, a new research project has launched for the development of a conceptual design of a further advanced SMR which aims for a naturally-safe and autonomous operation, so called Autonomous Transportable On-demand reactor Module (ATOM). Major design objectives of the ATOM system are focused on the soluble boron-free (SBF) primary coolant system which enables the SMR to operate automatically in a load following mode. For the secondary system, the SCO2 power conversion cycle with air-cooling system as a final heat sink is being considered. The air-cooling system is expected to show flexible response even to extreme environmental conditions, such as a desert where utilization of cooling water is limited. The objective of this study is a feasibility assessment for applying the air-cooling system as a final heat sink of the ATOM by means of experimental work. As a 1st phase of the ATOM development, we first conducted the experiments using a typically considered primary coolant, water-steam, to verify that air flow has enough cooling capability to remove developed heat which the coolant carries. An Integrated Condensation Loop with Air-cooling System (ICLASS) experimental facility with three pressure boundaries (Steam, coolant, and air) was established. The cooling capability of the air-cooling system was evaluated by varying steam mass flow rate, coolant flow rate, and air environment temperature as experiment variables. Overall heat transfer rate by condensation was compared with numerical simulations of a 1D thermal-hydraulics analysis code, using the MARS model of the ICLASS facility.

scholarly journals Application of reverse osmosis at NPP and verification of the process for primary coolant treatment in temelín nuclear power

2021 ◽  
Vol 7 (2) ◽  
pp. 1-7
Author(s):  
Skala M. ◽  
Kůs P. ◽  
Kotowski J. ◽  
Kořenková H.
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Boric Acid ◽  
Reverse Osmosis ◽  
Nuclear Power ◽  
Power Plants ◽  
Pure Water ◽  
Feed Solution ◽  
Primary Coolant ◽  
Purification System

Drained primary coolant from nuclear power plants containing boric acid is currently treated in the system of evaporators and by ion exchangers. Reverse osmosis as an alternative process to evaporator was investigated. Using reverse osmosis, the feed primary coolant is separated into two output streams: retentate and permeate. Retentate stream consists of concentrated boric acid solution together with other components, while permeate stream consists of purified water. In the first phase ofthe project the reverse osmosis modules from several manufactures were tested on a batch laboratory apparatus. Certain modifications to the pH of the feed solution were needed to enable the tested membranes to concentrate the H3BO3 in the retentate stream, separate from the pure water in the permeate stream. Furthermore, the separation capability for other compounds present in primary coolant such as K, Li or NH3 were evaluated. In the final phase of the project the pilot-plant unit of reverse osmosis was tested in nuclear power plant Temelín. It was installed in the Special Purification System SVO-6 for the regeneration of boric acid. The aim of the tests performed in Temelín nuclear power plant was to verify possible use of reverse osmosis for the treatment of primary coolant.

Optical Method for Controlling the Flow Rate of the Coolant in Nuclear Reactors

2021 ◽  
Author(s):  
Roman Davydov ◽  
Valentin Dudkin ◽  
Semen Logunov ◽  
Alexander Bobyl
Keyword(s):  
Flow Rate ◽  
Optical Method ◽  
Nuclear Reactors

The Evaluation of the PXQ for the Analysis of Cements and Related Materials

1958 ◽  
Vol 2 ◽  
pp. 215-227
Author(s):  
George Andermann ◽  
J. L. Jones ◽  
E. Davidson
Keyword(s):  
Flow Rate ◽  
Gas Flow ◽  
Applied Research ◽  
Production Control ◽  
Helium Flow ◽  
X Ray ◽  
Long Term Stability ◽  
Short And Long Term

AbstractThe analysis of cements and ores has been studied using the Applied Research Laboratories, Inc. Production Control X-ray Quantometer (PXQ), Elements included in the program were magnesium, aluminum, silicon, phosphorus, calcium and iron. The PXQ, utilizing the polychromator concept, allows the simultaneous determination of the listed elements.Focusing ADP, EDT, quartz and LiF crystals were used with flow Geigers or Multitrons. Helium paths were used as required. The choice of crystals, detectors, and slit widths was determined to give optimum results for each element.The effects of briquetting and ratioing to scattered background on accuracy were studied. Various instrumental factors such as helium flow rate, detector gas flow rate, short and long term stability were also investigated.

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