Flow-injection determination of boric acid concentration with conductometric detection

2018 ◽  
Vol 84 (12) ◽  
pp. 20-24
Author(s):  
V. S. Gursky ◽  
E. Yu. Kharitonova

The flow-injection determination of boric acid with conductometric detection in technological environments of the primary circuit of WWER-type nuclear power plant is described. The method consists in periodical dosing a fixed sample volume into the flow of the mannitol solution. As a of the Formation of an anionic boric acid complex with mannitol and equivalent amount of hydroxonium ions, results in an abrupt increase in the electrical conductivity, which is recorded by a conductometric detector. The hydraulic and measuring circuits of the analyzer are implemented using standard ionochromatographic equipment. It is shown than in the concentration range of the analyte 1 – 16 g/liter, the correcting additives of ammonium and potassium hydroxides do not interfere with the results of the analysis. To eliminate the interfering effect of correcting additives at low concentrations of boric acid (0.2 – 1.0 g/liter) we propose to use a Donnan dialysis through a cation exchange membrane. Optimal conditions of the analysis are specified and the metrological characteristics are determined. At a concentration of boric acid of 0.2 g/liter, the standard deviation does not exceed 2%.

Author(s):  
A. Traichel ◽  
F. Tardy ◽  
M. Mummert

A general overview of the existing radioactive inventory in the plant is necessary for the decommissioning of nuclear power plants. Based on the knowledge about radiological inventory, appropriate decommissioning techniques and procedures can be specifically used. In order to derive the existing radiological activity in the facility a study was carried out to obtain a representative overview of the total radiological situation at the NPP. Within a study a generic methodology for the radiological characterization was developed. This methodology has been applied on the CO2-circuit of the gas-cooled, graphite-moderated reactor Chinon A2 (MAGNOX type). This paper covers the implementation of an approach for characterisation of radiological inventory for decommissioning. The approach aims at the definition of the number and distribution of local sampling, required measurements as well as suitable measurement systems leading to a confident result with minimized effort in sampling. The paper covers two main objectives: 1. Methodology at and 2. Determination of radiological inventory based on measured data. The proposed methodology is a stepwise procedure which offers the possibility for minimizing the number of required measurements/sample analyses. At the first step the underlying system is an “as-simple-as-possible”-example with homogeneous contamination. In a second step the methodology is expanded to a more realistic and complex system, for which additional investigations have to be performed. The determination of the radiological inventory using the methodology has to consider a given confidence level and maximum allowed error. Therefore statistical assessment is widely used in estimations. The result of this first part of study generates the basis for further investigation. This comprises application of methodology to the mentioned technical system. Therefore corresponding measurement and analysis data have to be delivered and proven regarding adequacy for the proposed methodology. From the dataset various measurement systematic and retained parameters could be derived. The accuracy of given measured data was checked by further examination. The result of the performed analysis leads to a statement about the activity in the primary circuit. The result of this study is an comprehensive estimation of the activity by defined statistical processing of analysed data. The result consists moreover of the analysis of the measurement plan and of distribution and deviation within the measured data. Suggestions for further measurement campaigns are provided based on the deviations and inconsistencies of the data. With the help of these suggestions it should be possible to decrease the number of samples and measuring data as well as improve the comparability of separate measurement processes. Particular potential for improvement of the result for inventory can be seen in a deeper analysis of uncertainties, this was realised and will be explained in the paper.


1974 ◽  
Vol 57 (3) ◽  
pp. 636-641
Author(s):  
Modest Osadca ◽  
Mercedes Araujo

Abstract A simple, rapid, and sensitive chemical method is described for determining lasalocid sodium in finished poultry feeds and premixes. The drug is extracted with ethyl acetate directly from premixes and after a brief treatment with pH 4.7 buffer from finished feeds. Lasalocid sodium concentration is measured spectrofluorometrically and a correction for nonspecific fluorescence is determined after formation of a lasalocid- boric acid complex. Replicate assays of typical poultry mashes and pellets containing about 0.0075% lasalocid sodium yielded coefficients of variation of 2.8 to 5.0%. Average recovery of lasalocid sodium added in the laboratory at 0.0037, 0.0075, and 0.0112% was 90% with a pooled standard deviation of ±1.86%.


Author(s):  
Michel Bie`th

Decisions regarding the verification of design plant lifetime and potential license renewal periods involve a determination of the component and circuit condition. In Service Inspection of key reactor components becomes a crucial consideration for continued safe plant operation. The determination of the equipment properties by Non Destructive Techniques during periodic intervals is an important aspect of the assessment of fitness-for-service and safe operation of nuclear power plants The Tacis and Phare were established since 1991 by the European Union as support mechanisms through which projects could be identified and addressed satisfactorily. In Nuclear Safety, the countries mainly concerned are Russia, Ukraine, Armenia, and Kazakhstan for the Tacis programme, and Bulgaria, Czech Republic, Hungary, Slovak Republic, Lithuania, Romania and Slovenia for the Phare programme. The Tacis and Phare programs concerning the Nuclear Power Plants consist of: • On Site Assistance and Operational Safety, • Design Safety, • Regulatory Authorities, • Waste management, and are focused on reactor safety issues, contributing to the improvement in the safety of East European reactors and providing technology and safety culture transfer. The main parts of these programmes are related to the On-Site Assistance and to the Design Safety of VVVER and RBMK Nuclear power plants where Non Destructive Techniques for In Service Inspection of the primary circuit components are addressed.


1999 ◽  
Vol 21 (1) ◽  
pp. 1-9 ◽  
Author(s):  
Anthony R. J. David ◽  
Trevor McCormack ◽  
Paul J. Worsfold

The design, construction and performance of a remotely deployed submersible flow injection-based nutrient (total oxidized nitrogen) sensor are described. The sensor featured a custom-built microcomputer and a solid-state, flow-through spectrophotometric detector, and the derivatization chemistry was based on in-line coppercadmium reduction of nitrate to nitrite, and diazotization with N1NED and sulphanilamide. The limit of detection was 0.0014 mg l-1NO3-N and the linear range was 0.0014- 0.77 mg l-1with a 260 μl sample volume and a 20 mm path length flow cell. Results from submersed deployments in the Tamar estuary and North Sea are also reported.


2015 ◽  
Vol 17 (6) ◽  
pp. 4578-4588 ◽  
Author(s):  
Mari Kajiwara ◽  
Yoshio N. Ito ◽  
Yoshinobu Miyazaki ◽  
Takao Fujimori ◽  
Kô Takehara ◽  
...  

We fully elucidated the three-component reaction kinetics and thermodynamics of a boric acid complex with H-acid and salicylaldehyde using voltammetry.


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