\documentclass[12pt,a4paper]{report} \pagestyle{headings} \usepackage{enumerate} \usepackage{amsmath} \usepackage{verbatim} \usepackage{rotating} \usepackage{amssymb} \usepackage{graphicx} \usepackage{bm} \usepackage{color} \usepackage{soul} \usepackage[titletoc]{appendix} \usepackage{placeins} \usepackage{upgreek} \usepackage{pdfpages} \setcounter{secnumdepth}{2} \setcounter{tocdepth}{1} \begin{document} \includepdf[pages=1-last]{header.pdf} \setcounter{page}{1} \tableofcontents \chapter{Introduction} \section{Nuclear fusion} Fusion reactions form a branch of nuclear reactions in which two nuclei join together while energy is released (usually a significant amount). It is nuclear fusion that powers the Sun, and utilizing fusion reactions in a power plant could in future bring excellent source of energy to mankind, whose success and development is highly dependent on its ability to harness energy from natural sources. Such sources would have great advantage over fossil and fission power plants, as they would use much smaller amount of much cheaper fuel, be inherently safe and neither pollute the environment by exhaust gases nor produce significant amount of nuclear waste. The only major utilization of artificial fusion reactions took place in early 1950s when thermonuclear weapons were invented. Technology to use fusion for peaceful purposes has been developed since, but a lot of issues has been encountered and taming fusion has proven to be a challenge. \subsection{Coulomb barrier} \label{sec_coulombbarrier} In order to fuse, the two nuclei need to get very close to each other. Due to positive electric charge, the nuclei strongly repel each other, and high amount of energy has to be supplied to overcome this so-called Coulomb barrier. Although it is possible to accelerate a nucleus and let it hit the other one, it is not possible to build a power plant on this principle, because most of the energy is dissipated by scattering in the target material, and only a small fraction of the particles actually fuse. Better concept is \emph{thermonuclear} fusion. Instead of accelerating particles against a target, the fuel is heated to very high temperatures where their thermal kinetic energy allows the most energetic particles to overcome the barrier. Scattering thus does not mean losing energy from the system, it rather only redistributes energy between individual particles. \subsection{D-T fusion reaction} There are many fusion reactions possible, but when one considers energy of the Coulomb barrier, cross section for fusion, availability of the fuel etc., there is not many candidates left. The one that seems to be the easiest to use is D-T reaction: \[^2_1D\,+\,^3_1T\;\rightarrow \;^4_2He\,+\,^1_0n\,+\,17.6\,MeV\] The disadvantage is that the majority of the energy is released as kinetic energy of the neutron, which would place the device in high neutron-flux. Another issue is that one of the reactants is tritium, which is radioactive and difficult to obtain (although it should be possible to use the neutrons to breed tritium in other nuclear reactions). \subsection{Lawson criterion} As mentioned in section~\ref{sec_coulombbarrier}, basic principle in thermonuclear fusion is heating the fuel to very high temperatures (so high that any material is in a plasma state). In order to keep the plasma at this temperatures one has to find a way to cover energy losses. Because part of the fusion energy in D-T reaction is released as kinetic energy of the alpha particle which does not escape from the plasma (unlike the neutron), it is in principle possible to use this energy to compensate for energy losses from the plasma. This state is called \emph{ignition}, and the condition for it to happen can be matematically expressed as \[n\tau_E\geq f(T)\] where $n$ denotes plasma density and $\tau_E$ \emph{energy confinement time}, which describes rate at which energy is lost from the plasma. $f(T)$ is a function of temperature with a low at about 25 keV. For a given temperature the equation basically says that the quicker energy is lost from the plasma, the higher the density has to be in order to achieve ignition. \subsection{Tokamak} Plasma cannot be in touch with a vessel it is contained in, because a contact with anything would mean the plasma would rapidly cool. In order to achieve sustainable steady state plasma, ways were invented to avoid the contact with the walls. A plasma by definition contains charged particles, which makes it possible to control it with magnetic or electric fields. There are many different configurations that were studied, but the most successful and promising turned out to be a soviet device called \emph{tokamak}. The main part is a toroidal vacuum vessel with large coils around. These coils form strong toroidal magnetic field in the vessel. A small amount of gas is pumped into the well evacuated chamber and another coil induces electric field in the loop of gas, rapidly heats it up and turns it into plasma. Induced electric current passes through the plasma and heats it; at the same time this current creates another magnetic field that twists lines of force of toroidal field. The resulting shape of the field stabilizes the plasma and increases particle confinement time. The plasma is turbulent and very difficult to contain, and a lot of issues in both physics and technology has to be solved before a fusion power plant is built. In order to push the research further, a lot of diagnostic tools is needed to gain information about all processes that take place during a tokamak discharge. One of the many (that this paper mainly concerns with) is interferometric diagnostics to measure density. \section{GOLEM tokamak} \subsection{History} Tokamak GOLEM is one of the oldest tokamaks ever built, and the oldest still operational. Its rich history began in early 1960s, when it was built under a codename TM-1 as a small companion of tokamak T-1 at the Kurchatov institute in the Soviet Union. In mid-1970s it was moved to Czechoslovakia, where it was operated by Czechoslovak Academy of Sciences\footnote{Succeeded by Academy of Sciences of the Czech Republic} under the name CASTOR\footnote{\textbf{C}zech \textbf{A}cademy of \textbf{S}ciences \textbf{TOR}us}. A major refurbishment took place in mid-1980s. After ASCR acquired COMPASS tokamak from UKAEA\footnote{United Kingdom Atomic Energy Authority} in 2006, CASTOR tokamak was dismantled and donated to FNSPE CTU\footnote{Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University}, where it is operated under the name GOLEM and serves as an educational tool. \subsection{Parameters} Tokamak GOLEM is a conventional tokamak with circular cross-section limiter. Its major radius is $R=0.4\ m$ and minor radius (limiter) only $a=0.085\ m$, which makes it also the smallest operational device of its kind. There are 18 diagnostic ports in the internal liner. The magnetic field is produced by discharging a capacitor battery into 28 toroidal coils. \begin{table}[h] \centering \begin{tabular}{|l|l|} \hline Toroidal magnetic field & \textless 0.8 T \\ \hline Plasma Current & \textless 8kA \\ \hline Discharge Duration & 13 ms \\ \hline Central Electron Temperature & 80 eV \\ \hline Safety Factor at Plasma Edge & 15 \\ \hline Working Gas Pressure & 0-100 mPa \\ \hline Work Gas & H$_2$ (He) \\ \hline \end{tabular} \caption{Basic parameters of the GOLEM tokamak} \end{table} \begin{figure}[h] \centering \includegraphics[width=145mm]{golem.jpg} \caption{GOLEM tokamak photo (2015)} \end{figure} \FloatBarrier \subsection{Current status} \label{sec_golemhistorycurrentstatus} During its operation at FNSPE, some of the tokamak parts were exchanged for new ones. The control system was also updated and the tokamak is now controlled by computer. Some new features were lately introduced by the students (as mentioned above, the device serves as an educational tool). The tokamak is connected to the internet and all discharges and data from all available diagnostics are immediately publicly available. It is also possible to use the internet for remote control experiments. However, not all equipment that had been in use when the tokamak was stationed at ASCR is currently operational. Such is the case of an 4mm microwave interferometer, which was never successfully reinstalled (although a partially successful attempt has been made, as will be described in section~\ref{sec_2011}). As a result, currently there is no diagnostics that could provide reliable information on plasma density. \section{Goals of this thesis} \begin{itemize} \item Provide detailed information on microwave plasma density measurement, describe basic physical phenomena regarding the topic and show issues that arise and how to deal with them. \item Make the interferometer on GOLEM tokamak operational again, so that the important information on plasma density is available to future researchers. \item Include the interferometer output into GOLEM diagnostic system, which has changed significantly since CASTOR times. \item Perform independent verification of the measured density (if possible). \end{itemize} \chapter{Interferometric measurement of plasma density} \chaptermark{Interferometric density measurement} Interferometry is in general a measurement method which utilizes electromagnetic radiation interference effect. A typical example comprises of a source that emits waves at some known wavelength. The wave is split into two, one serves as a reference, the other passes through a sample. By comparing phases of the two waves one can measure difference of the optical path and index of refraction of the sample. This chapter describes principles of several basic microwave components, gives relation between phase shift in the plasma and its density and presents so called frequency modulating interferometer. \section{Microwave technology preliminaries} Microwave interferometry logically relies on microwave technology knowledge. The most important parts that will be used are the microwave generator, waveguides and detection diode. Only the very basic principles of their operation will be described. For detailed description please see specialized literature~\cite{bib_zacek}\cite{bib_kvasil}\cite{bib_gardiol}. \subsection{Gunn diode oscillator} Gunn diode is a solid state semiconductor device. Its function is based on Gunn effect discovered by J. B. Gunn in 1963. Unlike other diodes there is no P-N junction, but only N-doped semiconductor is used. Three regions exist -- heavily doped electrodes and a thin layer of lightly doped semiconductor in between. The electronic band structure contains a third band (aside from valence and conductive bands) which the electrons can occupy -- it is located above the conductive band, so the electrons must have certain threshold energy to reach it (this is called electron transfer). The mobility in the third band is lower than in conductive band. This produces a negative differential resistance region in the I-V characteristics because after certain voltage is applied electron transfer starts to occur, electrons start to occupy the third band and their mobility (and therefore current) decreases. This first occurs at the doping level boundary at the cathode due to the inhomogenity there. An electron in the third band creates an non-homogenity in the electric field and electrons slowed by this field tend to bunch together, creating a high intensity field domain moving toward the anode at the speed of electrons in the upper band. The local concentration of electrons thus reduces electric field in the rest of the material (a large portion of the biasing voltage appears at the domain) preventing creation of another domain, until the first domain arrives at the anode. The process then repeats. \newline \begin{figure}[h] \centering \includegraphics[width=80mm]{gunn.jpg} \caption{Gunn diode oscillator~\cite{bib_gardiol}}\label{fig_gunn} \end{figure} Frequency of oscillations depends mostly on the material thickness, but can also be changed by placing the diode biased into negative resistance region into a resonant cavity. This is how Gunn diode microwaves oscillators are constructed (see figure~\ref{fig_gunn}). The cavity dimensions can usually be adjusted by a tuning piston, allowing to change the frequency in a narrow range. Additional tuning can be achieved electrically. Commercially available generators often use a varactor diode as a voltage-controlled capacity to allow rapid changes of the oscillation frequency. Output power can be as high as 100~mW, efficiency is usually low (several percent). \subsection{Waveguides\label{sec_waveguides}} Although microwaves (like all electromagnetic radiation) propagate through free space, it is necessary to have some way of guiding them where they are to be used. Waveguides are a way of achieving this. A waveguide is generally a hollow pipe (not necessarily circular in cross-section) made of conductive material. The wave travelling inside is thus confined to the inside and no energy is lost by radiation. Exact solution can be obtained by solving Maxwell equations with proper boundary conditions describing the waveguide. \newline The conclusion from the analysis (that will not be done here) is that for a given waveguide, only frequencies above certain so called \emph{cut-off frequency} can propagate. Frequencies significantly higher than this cut-off propagate almost at c\footnote{speed of light in vacuum}, decreasing the frequency reduces group velocity and increases wavelength. As frequency approaches cut-off, group velocity approaches zero (and wavelength infinity). The wave can propagate in multiple modes (different distribution of electric and magnetic field). The modes are classified as TE (transverse electric -- electric field component along the direction of propagation is zero), TM (transverse magnetic) and TEM (transverse electric and magnetic)\footnote{It can be shown that hollow waveguide cannot support TEM modes.}. Every mode has different cut-off frequency for a given waveguide. That means that at high frequencies more modes can be present. As frequency decreases, single modes vanish one by one until a last one remains. This mode is called \emph{dominant mode}. The dominant mode is the one used during measurements and all other modes are supressed (easiest way is to choose proper waveguide size for a given frequency). \subsubsection{Rectangular waveguide} Most waveguides used at GOLEM are of rectangular cross section. Let us denote the sides $a$, $b$ and assume $a>b$. The cut-off frequency for TE$_{mn}$ and TM$_{mn}$ modes is \begin{equation} f_c=\frac{c}{2\pi} \sqrt{\left(\frac{m\pi}{a}\right)^2+\left(\frac{n\pi}{b}\right)^2} \end{equation} It can be shown however, that TM mode with either m=0 or n=0 cannot exist in rectangular waveguide. The dominant mode is therefore TE$_{10}$ and its cut-off wavelength is $2a$. Electric and magnetic field lines are shown in figure~\ref{fig_rectangularte}. The electric field is parallel to the shorter side of the waveguide with a maximum value in the middle. \begin{figure}[h] \centering \includegraphics[width=60mm]{rectangularte.png} \caption{TE$_{10}$ mode in rectangular waveguide (solid lines -- E-field, dashed lines -- H-field)~\cite{bib_fig_modes}}\label{fig_rectangularte} \end{figure} Waveguides are usually made so that $a=2b$ to allow 2:1 dominant mode bandwidth and simultaneously maximize power that can be transferred before dielectric breakdown occurs. Table of waveguide types is shown in appendix~\ref{app_waveguides}. Given that microwave generator used at GOLEM has frequency of 71~GHz it is clear that only V,E and W band waveguides can be used (U would allow TE$_{11}$ mode to propagate, F would not allow 71~GHz through at all). \newline Although it has been noted that no energy is lost by radiation, waveguides still attenuate the wave that passes through them. The reason is that the wave induces current in the waveguide wall which results in resistive energy losses. A detailed analysis is complicated and will not be presented here, but in simple terms -- the smaller the waveguide, the higher the attenuation (as seen in appendix~\ref{app_waveguides}). In certain applications it might therefore be necessary to use larger waveguides than calculated from desired cut-off frequency for cutting distance. Such waveguides enable higher modes to propagate so it is necessary to transition to the proper waveguide size when the signal is manipulated with to supress them (in case they appear, which does not have to happen). \subsubsection{Circular waveguide} The situation with circular waveguide is similar to rectangular ones. At GOLEM tokamak they are only used at one place and cannot be manipulated with, so detailed description is omitted. Dominant mode is denoted~T$_{11}$ -- see figure~\ref{fig_circularte} to see the field lines. \begin{figure}[h] \centering \includegraphics[width=40mm]{circularte.png} \caption{TE$_{11}$ mode in circular waveguide (solid lines -- E-field, dashed lines -- H-field)~\cite{bib_fig_modes}}\label{fig_circularte} \end{figure} \subsection{Detection diode} The microwave signal is detected by means of a detection diode at GOLEM tokamak. It is a point-contact diode mounted inside a waveguide so that the E-field of the wave is perpendicular to the point. The waveguide assembly the diode is in is terminated by a short that reflects the incoming wave and creates a standing wave. The diode junction is located precisely one quarter of a wavelength from this short, which places it into first standing wave maximum. The voltage across the junction is approximately proportional to microwave power (for reasonably small power). A Russian-made detection diode D-404 is shown in figure~\ref{fig_d404} for illustration. \newline \begin{figure}[h] \centering \includegraphics[width=70mm]{d404.jpg} \caption{D-404 detection diode (waveguide dimensions are about 7.1x3.55~mm -- Ka band)}\label{fig_d404} \end{figure} \section{Plasma behaviour and index of refraction} \label{sec_plasmabehaviour} When one wants to use interferometry to measure plasma density, it is obviously essential to know how plasma reacts to electromagnetic radiation and what its index of refraction depends upon. Electromagnetic radiation in a plasma in a presence of magnetic fields propagates in different modes, depending on direction of its $\bm{k}$, $\bm{E}$ and $\bm{B}$ vectors with respect to the external magnetic field $\bm{B_0}$ direction\cite{bib_kulhanek}. Providing that $\bm{k}\cdot \bm{B_0}=0$ and $\bm{E}\parallel \bm{B_0}$, only so called \emph{O-wave} (ordinary wave) propagates. By introducing \emph{plasma frequency} \[\omega_p^2={\frac{ne^2}{\varepsilon_0 m}}\] ($n$ denotes plasma density, $e$ elementary positive charge, $\varepsilon_0$ vacuum permittivity and $m$ electron mass), the index of refraction for O-wave at angular frequency $\omega$ can be written as (the last approximation is valid for $\omega>>\omega_p$)\footnote{To keep things simple, validity of the approximation will be assumed throughout the rest of this paper. For average plasma density of $10^{19}\, \textrm{m}^{-3}$ (which is higher than usually observed density) the approximation results in an error of about 4~\%. That is reasonable, considering that without the approximation, following steps would get very complicated (section~\ref{sec_lineintegrateddensity}) and would require some estimation anyway.} \begin{equation} N_O=\sqrt{1-\frac{{\omega _p}^2}{\omega ^2}}\approx 1-\frac{ne^2}{2\varepsilon_0m\omega^2} \label{eqn_indexofrefraction} \end{equation} Two very important points can be derived from the expression: \begin{itemize} \item{The index of refraction is always smaller than 1 and decreases as density increases (for $\omega>>\omega_p$ approximately linearly)} \item{O-wave only propagates when $\omega>\omega_p$} \end{itemize} Because plasma frequency increases with density, for every wave frequency $\omega$ there is a \emph{critical density} \[n_c=\frac{\varepsilon_0m}{e^2}\omega^2\] which is the highest density that allows the wave to propagate. For density higher than the critical density, plasma frequency is higher than the wave frequency, which results in imaginary index of refraction and the wave therefore cannot propagate and is reflected. This places a lower limit on the frequency of the interferometer. \section{Relation between index of refraction and change of phase} However, the index of refraction cannot be directly measured and this is where interferometry comes in. The diagnostic beam passes through the plasma and the index of refraction is calculated from the resulting change of phase. Let us assume that $\lambda_1=\frac{c}{f}$ denotes vacuum wavelength of the radiation, while $\lambda_2=\frac{c}{Nf}$ is the wavelength in a medium with index of refraction $N$. Providing that path length through the medium is $L$ and both waves have zero phase when entering the medium, the phases $\varphi_{1,2}$ at the end of the path can be written as \[\varphi_{1,2}=2\pi\frac{L}{\lambda_{1,2}}\\\] And therefore \begin{equation} \Delta\varphi=\varphi_2-\varphi_1=\frac{\omega L}{c}\left(N-1\right) \label{eqn_phaseshift} \end{equation} As mentioned earlier, the index of refraction of the tokamak plasma is less than unity, and can be calculated from equation~\ref{eqn_indexofrefraction}. Equation~\ref{eqn_phaseshift} then gives \begin{equation} \Delta\varphi=-\frac{\omega L}{c}\cdot \frac{ne^2}{2\varepsilon_0 m \omega^2}=-\frac{Lne^2}{2c\varepsilon_0 m\omega} \label{eqn_phaseshift2} \end{equation} The phase shift in presence of the plasma is negative, which means the optical path is shorter. If one wants to simulate plasma appearance by changing the length of the waveguide, it is necessary to \emph{shorten} the waveguide, which may seem counter-intuitive to some. \section{Line-integrated density\label{sec_lineintegrateddensity}} It may seem that calculating density from equation~\ref{eqn_phaseshift2} is straightforward. However, the above derivation was based on the fact that the density distribution is uniform, which is rarely the case in practice. By looking on the right-hand side one can easily see that the correct equation for non-uniform density profile is \[\Delta\varphi=-\frac{e^2}{2c\varepsilon_0 m\omega}\int_0^L n(l) \, dl\] and therefore \begin{equation} \underbrace{\int_0^L n(l) \, dl}_{n_i}=-\frac{2c\varepsilon_0 m\omega \Delta\varphi}{e^2} \label{eqn_phaseshift3} \end{equation} The integral is obviously line integral along the wave path parametrised by its length. Without knowing the dependence $n(l)$ it is only possible to calculate the value of the integral. Therefore \textbf{the quantity that can be calculated from the measured phase shift is integral density along the path of the diagnostic wave} \[n_i=\int n(l) \, dl \quad [m^{-2}]\] \newline The integral density is not relevant and it is needed to calculate more important quantities, namely average density along the path $n_L\;[m^{-3}]$ and maximal density in the plasma center $n(0)\;[m^{-3}]$. This calculation requires to know other parameters of the plasma, specifically \begin{itemize} \item{Length of the path in the plasma $L$ to determine $n_L$} \item{Length of the path in the plasma and density profile along this path to determine $n(0)$} \end{itemize} The former can be obtained from other diagnostics (or estimated from limiter diameter), the latter requires estimation, which makes the interferometric measurement of plasma density complex. \section{Calculating $n_L$ and $n(0)$} As mentioned above, integral density along the path $n_i=\int n(l) \, dl$ is not very suitable, and the question arises how to use it to calculate more convenient average density along the line of sight $n_L$ and central density $n(0)$. Let us assume, that the path length $L$ has been obtained from another diagnostics and density profile $n(r)$ is estimated (except for a multiplicative constant). \newline Calculating $n_L$ is straightforward and needs no commentary: \[n_L=\frac{1}{L}\cdot n_i \qquad [m^{-3}]\] Calculating $n(0)$ is more difficult, and this issue will be dealt with separately for circular and vertically elongated plasma. \subsection{Calculating $n(0)$ for circular plasma} In order to calculate $n(0)$, density profile $n(r)$ has to be estimated. Let us assume parabolic density profile \[n(r)=n(0)\left(1-\frac{r^2}{a^2}\right)\] where $r$ is the distance from plasma center and $a$ minor radius. Now it is possible to evaluate the relation between $n(0)$ and integral density $n_i$ by integrating the above equation along the line of sight. \[n_i=\int_{-a}^{a}n(r) \, dr=n(0)\int_{-a}^{a}\left(1-\frac{r^2}{a^2}\right) \, dr=\frac{4}{3}an(0)\] And because $L=2a$, the expression can be rearranged as \[n(0)=\frac{3}{2}\frac{n_i}{L}=\frac{3}{2}n_L\] \subsection{Calculating $n(0)$ for vertically elongated plasma} Let us assume that the plasma originally circular with minor radius $a_c$ was vertically elongated to minor radius $a_e$, and that the density profile in the outer part is unchanged, whereas in the center the density is constant, i.e. \[ n(r)=\left\lbrace \begin{array}{l l l}n(0)\left(1-\frac{\left(r-\left(a_e-a_c\right)\right)^2}{a_c^2}\right) &\,\text{if }r\in (-a_e,-(a_e-a_c))\cup (a_e-a_c,a_e)\\ \\n(0) &\,\text{if }r\in (-(a_e-a_c),a_e-a_c)\end{array} \right. \] The integral density in this case is obviously higher than in the case of circular plasma, specifically it is \[n_i=\frac{4}{3}a_cn(0)+2(a_e-a_c)\cdot n(0)=\frac{2}{3}n(0)\left(3a_e-a_c\right)\] and therefore \[n(0)=\frac{3n_i}{2(3a_e-a_c)}\] \section{Specific issues for tokamak plasma\label{sec_specificissues}} So far the method seems simple, but one has to realise that it is not possible to measure arbitrary large difference of phase. Phase differences of the form $2k\pi,k\in\mathbb{Z}\, \mathrm{(whole\, number)}$ are equivalent, so no matter what detector is used, the actual phase difference can be different by any whole multiple of $2\pi$. Whenever the difference is greater than $2\pi$, it is not measured correctly. See Fig.~\ref{fig_fringes} as an illustration. Looking at~\ref{eqn_phaseshift2}, one might get an impression that using frequency high enough to make the phase change small can resolve the problem. However, using too high frequencies results in different issues (e.g. high sensitivity to vibrations due to shorter wavelength). As mentioned in section~\ref{sec_plasmabehaviour}, there is also a lower limit on the frequency of the diagnostic wave. Considering plasma density $10^{19}\;m^{-3}$ (which is the order of plasma density in a tokamak), this limit is roughly 30 GHz (the frequency has to be higher in order for the approximation $\omega>>\omega_p$ to be valid). The wave therefore has to be in microwave range. At GOLEM tokamak, it is roughly 71~GHz with a path length of 0.17 m (limiter diameter). It is therefore possible to calculate what density increase results in a fringe in the data. By substituting $\Delta\varphi=-2\pi$ (phase difference is negative, as shown above) into equation~\ref{eqn_phaseshift2} and solving for $n$, one gets an average density (let us call it \emph{fringe density}) $n_f$: \[n_f=\frac{4\pi\varepsilon_0 m \omega c}{e^2L}\approx 3.11\cdot 10^{18}\,m^{-3}\] That means there can be several fringes observed during a shot. It is possible to follow the record and remove the discontinuities between the fringes. However, when the number of fringes is too high, this process is not possible, because whenever a part of the record is lost (e.g. due to refraction of the wave), several fringes can be missed and one loses count. It is then impossible to continue at the correct spot. \begin{figure} \centering \includegraphics[width=125mm]{fringes.png} \caption{Top - actual phase difference, bottom - measured phase difference (illustrative); the original signal is only possible to reconstruct when there are no gaps in the measured signal}\label{fig_fringes} \end{figure} \section{Frequency-modulating interferometer\label{sec_phasemodullatinginterferometer}} As described above, measuring line integrated plasma density can be done by measuring phase shift of the diagnostic wave after it passes through the plasma. In order to achieve this, the wave is split before entering the plasma. One wave is used as a reference (and does not pass through the plasma), the other wave is used as the diagnostic wave. Mutual phase shift changes are result of the plasma influence. Measuring the mutual phase shift can be performed by adding the waves together, and calculate the phase shift from the amplitude of the resulting wave. However, this amplitude depends not only on the phase shift, but also on the amplitude of the two interfering waves (which is an obvious fact). Since the amplitudes do not carry any information necessary to calculate density, a method to eliminate influence of the amplitudes is desired. One of possible solutions to this problem is to modulate the frequency of the wave. This type of interferometer is called~\emph{Wharton interferometer}\cite{bib_zacek}. \subsection{Principle of operation\label{sec_fmiprinciple}} Let us first assume there is no plasma in the examined volume. As in the general case, the generated wave is split into two -- one passes through the plasma, the other is used as a reference. The diagnostic wave passes through a long waveguide, so the path it travels is longer than the path of the reference wave. Let $\Delta L$ denote the path difference. The frequency of the wave generator is periodically changed by a sawtooth voltage signal. After the two waves interfere, a series of interference maxima will be created, because changing the frequency results in change of the relative phase difference between the two waves. Let $\Delta f$ denote frequency change during modulation and $c$ speed of light in a vacuum. A simple calculation shows that with frequency change $\Delta f$ the change of the phase difference is \footnote{The square root compensates for dispersion of the waveguide (a small change during frequency sweep is neglected ($\Delta f<