scholarly journals ICP-MS analysis of fission product diffusion in graphite for high-temperature gas-cooled reactors

2015 ◽  
Author(s):  
◽  
Lukas Michael Carter
Keyword(s):  
High Temperature ◽  
Fission Product ◽  
Diffusion Coefficients ◽  
Inductively Coupled Plasma ◽  
Nuclear Reactor ◽  
Fission Products ◽  
Release Rates ◽  
Inductively Coupled ◽  
Icp Ms ◽  
High Temperature Gas

High-temperature gas-cooled reactors (HTGRs) are one of the candidates being considered for the replacement of current nuclear reactor designs. Diffusion coefficients for fission products in HTGR graphite are required for estimation of fission product release rates from such reactors. We developed a method for analysis of fission product of fission product surrogate release rates from heated graphite samples. The graphite samples were infused with fission product surrogate material, and material which diffused from the graphite samples was transported via a carbon aerosol laden He jet system to an online inductively coupled plasma mass spectrometer for quantification of the release rate. Diffusion coefficients for cesium in IG-110 and NBG-18 grade nuclear graphites are reported.

scholarly journals Analysis of whole blood by ICP-MS equipped with a high temperature total sample consumption system

2017 ◽  
Vol 32 (1) ◽  
pp. 78-87 ◽  
Author(s):  
Águeda Cañabate ◽  
Esperanza García-Ruiz ◽  
Martín Resano ◽  
José-Luis Todolí
Keyword(s):  
High Temperature ◽  
Whole Blood ◽  
Inductively Coupled Plasma ◽  
Total Sample ◽  
Sample Introduction ◽  
Element Analysis ◽  
Inductively Coupled ◽  
System P ◽  
Icp Ms ◽  
Plasma Mass Spectrometry

In this work, the performance of a high temperature torch Integrated Sample Introduction System (hTISIS) using inductively coupled plasma mass spectrometry (ICP-MS) for the multi-element analysis of whole blood is evaluated.

scholarly journals Development of Analytical Procedures for Chemical Characterization of Substrates for the Production of TRISO Coated Particles as Nuclear Fuel in High Temperature Gas-Cooled Reactors

2020 ◽  
Vol 12 (17) ◽  
pp. 7221
Author(s):  
Ewelina Chajduk ◽  
Paweł Kalbarczyk ◽  
Jakub Dudek ◽  
Marta Pyszynska ◽  
Anna Bojanowska-Czajka ◽  
...  
Keyword(s):  
High Temperature ◽  
Nuclear Fuel ◽  
Inductively Coupled Plasma ◽  
Chemical Characterization ◽  
Quantitative Chemical Analysis ◽  
Coated Particles ◽  
Icp Ms ◽  
Analytical Procedures ◽  
High Temperature Gas

High temperature gas-cooled reactors have recently gained importance as a source of electricity and process heat. Nuclear fuel used in these reactors consists of TRISO (TRiple coated ISOtropic) coated particles, where spherical grains of UO2 or UC2 or UCO kernel are covered with four successive layers consisting of pyrolytic carbon and silicon carbide. Of great importance is the chemical purity of reagents and substances used for the production of TRISO coated fuel particles. Analytical techniques ensuring the determination of elements at trace levels are inductively coupled plasma mass spectrometry (ICP-MS) and neutron activation analysis (NAA). They were applied in this work for the chemical characterization of substrates used for TRISO fuel production. Two analytical procedures were developed: the first, where materials are analyzed using ICP-MS, and the second with the aid of NAA. Successive stages of these procedures are described with details. Results of quantitative chemical analysis of examined substances are reported as well as detection limits for the investigated elements. Moreover, the expanded uncertainties estimated for the determined elements while employing the devised analytical procedures are presented.

Mg diffusion in forsterite from 1250–1600 °C

2020 ◽  
Vol 105 (4) ◽  
pp. 525-537 ◽  
Author(s):  
Michael C. Jollands ◽  
Irina Zhukova ◽  
Hugh St.C. O'Neill ◽  
Jörg Hermann
Keyword(s):  
Diffusion Coefficients ◽  
Inductively Coupled Plasma ◽  
Tracer Diffusion ◽  
Ion Microprobe ◽  
Inductively Coupled ◽  
Icp Ms ◽  
Order Of Magnitude ◽  
Plasma Mass Spectrometry ◽  
The Difference ◽  
Tracer Diffusion Coefficients

Abstract 26Mg tracer diffusion coefficients were determined in single crystals of pure synthetic forsterite (Mg2SiO4). Isotopically enriched powder sources both acted as the 26Mg source and buffered the activities of silica (aSiO2) at forsterite + protoenstatite (Mg2Si2O6) (high aSiO2) and forsterite + periclase (MgO) (low aSiO2). Experiments were conducted at atmospheric pressure between 1250 and 1600 °C, and at oxygen fugacities (fO2s) between 10–12 bars (CO-CO2 mix) and 10–0.7 bars (air). The resulting diffusion profiles were measured along the three principal crystallographic axes (a, b, and c; ||[100], ||[010], ||[001]) using laser ablation–inductively coupled plasma–mass spectrometry (LA-ICP-MS), with a quadrupole mass spectrometer. These measurements were corroborated by ion microprobe using the sensitive high resolution ion microprobe-reverse geometry (SHRIMP-RG) instrument. Mg tracer diffusion is anisotropic, with D[001] > D[010] > D[100], the difference in diffusion coefficients varying by about one order of magnitude at a given temperature with crystallographic orientation. Diffusion is faster in protoenstatite-buffered than periclase-buffered conditions, again with around one order of magnitude difference in diffusivity between buffering conditions. There is no apparent effect of fO2 on diffusion. A global fit to all data, including data from Chakraborty et al. (1994) and Morioka (1981) yields the relationship: log 10 D = log 10 D 0 ( m 2 s - 1 ) + 0 . 61 ( ± 0 . 03 ) log 10 a SiO 2 + - 359 ( ± 10 ) kJ / mol 2 . 303 R T where log10D0 is –3.15 (±0.08), –3.61 (±0.02), and –4.01 (± 0.05) m2 s–1 for the [001], [010], and [100] directions, respectively (1 s.d.). The LA-ICP-MS technique reproduces diffusion coefficients determined by SHRIMP-RG, albeit with slightly different absolute values of isotope ratios. This shows that LA-ICPMS, which is both accessible and rapid, is a robust analytical method for such tracer diffusion studies.

Nonstoichiometry in KTP and Nb: KTP crystals by high-temperature solutions method

2015 ◽  
Vol 24 (04) ◽  
pp. 1550043 ◽  
Author(s):  
Xiaofei Hao ◽  
Chengguo Jin
Keyword(s):  
High Temperature ◽  
Photoelectron Spectroscopy ◽  
Inductively Coupled Plasma ◽  
Low Oxygen ◽  
High Potassium ◽  
Niobium Content ◽  
Inductively Coupled ◽  
Icp Ms ◽  
Temperature Solution ◽  
Mass Spectometry

Nonstoichiometry could cause many point defects and limit the application of KTP crystal. Nonstoichiometry in KTP and Nb:KTP crystals by high-temperature solution method were studied by laser-ablation inductively coupled plasma mass spectometry (LA-ICP-MS) and X-ray photoelectron spectroscopy (XPS). The formation of high potassium and Ti[Formula: see text] centers in KTP and Nb:KTP crystals was analyzed. The effect of niobium on nonstoichiometry in Nb:KTP crystal was discussed. The results showed that high potassium, low phosphate, and low oxygen existed in KTP and Nb:KTP crystal samples. Low phosphate and low oxygen in crystal samples resulted from phosphate volatilization, which could be inhibited by the increase of niobium content. Meanwhile, Ti[Formula: see text] centers in crystal samples were original and formed during crystal growth, and were generated with high potassium simultaneously.

scholarly journals Cerebrospinal fluid elemental analysis by using a total sample consumption system operated at high temperature adapted to inductively coupled plasma mass spectrometry

2017 ◽  
Vol 32 (10) ◽  
pp. 1916-1924 ◽  
Author(s):  
Águeda Cañabate ◽  
Esperanza García-Ruiz ◽  
Martín Resano ◽  
José-Luis Todolí
Keyword(s):  
Mass Spectrometry ◽  
Cerebrospinal Fluid ◽  
High Temperature ◽  
Elemental Analysis ◽  
Inductively Coupled Plasma ◽  
Total Sample ◽  
Inductively Coupled ◽  
Icp Ms ◽  
Plasma Mass Spectrometry ◽  
Consumption System

Cerebrospinal fluid (CSF) samples have been accurately analyzed by means of a total sample consumption system adapted to ICP-MS.

scholarly journals Studies on hydrometallurgical processes using nuclear techniques to be applied in copper industry. I. Application of 64Cu radiotracer for investigation of copper ore leaching

Nukleonika ◽  
2018 ◽  
Vol 63 (4) ◽  
pp. 123-129 ◽  
Author(s):  
Tomasz Smoliński ◽  
Marcin Rogowski ◽  
Marcin Brykała ◽  
Marta Pyszynska ◽  
Andrzej G. Chmielewski
Keyword(s):  
Nitric Acid ◽  
Neutron Activation ◽  
Sulphuric Acid ◽  
Inductively Coupled Plasma ◽  
Nuclear Reactor ◽  
Copper Ore ◽  
Inductively Coupled ◽  
Icp Ms ◽  
Online Measurements ◽  
Plasma Mass Spectrometry

Abstract Scientifi c objective of this work was elaboration of radiometric method for the development of hydrometallurgical process for recovery of Cu from the copper ore. A neutron activation analysis (NAA) was identifi ed as a very convenient tool for the process investigation. The samples of copper ore were activated in a nuclear reactor. The parameters of the neutron activation were calculated. Radioisotope 64Cu was selected as an optimal tracer, and it was used for the investigation of the leaching process. During the experiments, various processes applying leaching media such as sulphuric acid, nitric acid, and organic acids were investigated. The recovery of the metals using sulphuric acid was insuffi cient, around 10%. Investigated organic media also did not meet expectations. The best results were obtained in experiments with nitric acid. Up to 90% of Cu and other metals were extracted from the copper ore. Copper concentration calculations obtained by NAA were confi rmed by inductively coupled plasma mass spectrometry (ICP-MS) technique. Both techniques gave comparable results, but the advantage of the NAA is a possibility for easy online measurements without shutting down or disturbing the system.

scholarly journals Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model

2021 ◽  
Vol 2021 ◽  
pp. 1-8
Author(s):  
Chao Fang ◽  
Chuan Li ◽  
Jianzhu Cao ◽  
Ke Liu ◽  
Sheng Fang
Keyword(s):  
High Temperature ◽  
Source Term ◽  
Fission Products ◽  
Release Rates ◽  
Time Step ◽  
The Difference ◽  
Advanced Nuclear System ◽  
Fuel Elements ◽  
Term Analysis ◽  
High Temperature Gas

The radiation safety design and emergency analysis of an advanced nuclear system highly depends on the source term analysis results. In modular high-temperature gas-cooled reactors (HTGRs), the release rates of fission products (FPs) from fuel elements are the key issue of source term analysis. The FRESCO-II code has been established as a useful tool to simulate the accumulation and transport behaviors of FPs for many years. However, it has been found that the mathematical method of this code is not comprehensive, resulting in large errors for short-lived nuclides and large time step during calculations. In this study, we used the original model of TRISO particles and spherical fuel elements and provided a new method to amend the FRESCO-II code. The results show that, for long-lived radionuclides (Cs-137), the two methods are perfectly consistent with each other, while in the case of short-lived radionuclides (Cs-138), the difference can be more than 1%. Furthermore, the matrix method is used to solve the final release rates of FPs from fuel elements. The improved analysis code can also be applied to the source term analysis of other HTGRs.

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