The distribution of cases of bacteriuria according to the age of the studied groups.
\r\n\t
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Dr. Li’s research focuses on the vibration, fatigue, damage, fracture, reliability, safety and durability of aircraft and aero engine. In this research area, he is the first author of 184 SCI journal publications (49 JCR Q1), 8 monographs, 3 edited books, 3 textbooks, 3 book chapters, 30 Chinese Patents, 2 US Patents, 2 Chinese Software Copyright, and more than 20 refereed conference proceedings. He has been involved in different projects related to structural damage, reliability, and airworthiness design for aircraft and aero engines, supported by the Natural Science Foundation of China, COMAC Company, and AECC Commercial Aircraft Engine Company.",institutionString:"Nanjing University of Aeronautics and Astronautics",position:null,outsideEditionCount:0,totalCites:0,totalAuthoredChapters:"3",totalChapterViews:"0",totalEditedBooks:"3",institution:{name:"Nanjing University of Aeronautics and Astronautics",institutionURL:null,country:{name:"China"}}}],coeditorOne:null,coeditorTwo:null,coeditorThree:null,coeditorFour:null,coeditorFive:null,topics:[{id:"14",title:"Materials Science",slug:"materials-science"}],chapters:null,productType:{id:"1",title:"Edited Volume",chapterContentType:"chapter",authoredCaption:"Edited by"},personalPublishingAssistant:{id:"418641",firstName:"Iva",lastName:"Ribic",middleName:null,title:"M.Sc.",imageUrl:"https://mts.intechopen.com/storage/users/418641/images/16830_n.png",email:"iva.r@intechopen.com",biography:"As an Author Service Manager my responsibilities include monitoring and facilitating all publishing activities for authors and editors. 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Kawsar Alam",coverURL:"https://cdn.intechopen.com/books/images_new/6805.jpg",editedByType:"Edited by",editors:[{id:"199691",title:"Dr.",name:"Md. Kawsar",surname:"Alam",slug:"md.-kawsar-alam",fullName:"Md. Kawsar Alam"}],productType:{id:"1",chapterContentType:"chapter",authoredCaption:"Edited by"}}]},chapter:{item:{type:"chapter",id:"77619",title:"Breakthrough Host Defense: UTI in Pregnant Women in Comparsion to Non-Pregnant",doi:"10.5772/intechopen.98846",slug:"breakthrough-host-defense-uti-in-pregnant-women-in-comparsion-to-non-pregnant",body:'When compared to non-pregnant women, the risk of urinary tract infection (UTI) with bacteriuria increases considerably during pregnancy. Infection with bacteriuria during pregnancy has been linked to an increased risk of pyelonephritis [1]. Several physiological changes occur during normal pregnancy, including an increase in the volume of vascular and interstitial of the renal system, which results in a rise in kidney dimension of roughly 1 cm and a 30% rise in renal volume. In addition, by mid-pregnancy, around 80% of women will have dilated upper urinary tracts, ureters, pelvis, and calycle area. The right side of the body experiences dilation more frequently than the left [2]. Hydronephrosis and hydroureter, respectively, are dilations of the kidney and ureter that occur most commonly during the second trimester and last until birth. This dilation can be caused by both hormonal and mechanical factors; an increase in progesterone hormone levels causes a decrease in bladder and ureteral tone [3]. Urinary stasis was caused by mechanical causes such as gravid uterine compression paired with smooth muscle relaxation, which slowed ureter peristalsis and increased bladder volume capacity. Pregnancy-induced alterations in urine pH, osmolality, and glycosuria may further amplify bacterial growth [2]. Symptomatic infections (acute cystitis, acute pyelonephritis) occur when bacteria invade urinary tract tissues and trigger an inflammatory reaction, whereas asymptomatic bacteriuria (ASB) occurs when bacteria grow in urine without presenting symptoms of acute UTI [1]. Asymptomatic bacteriuria is more common in pregnant women than in non-pregnant women, and it is frequently underreported since diagnosis is difficult owing to the lack of particular symptoms or signs, whereas symptomatic bacteriuria creates no concerns because diagnosis and treatment are simple [1]. The most prevalent medical complication during pregnancy is urinary tract infection (UTI), which accounts for 20% of pregnancies and 10% of antepartum hospitalizations [4, 5, 6]. The most common bacterium that causes UTI in pregnant and nonpregnant women is
This case–control research comprised 30 pregnant women and 30 non-pregnant women who visited Al-zahraa Teaching Hospital’s outpatient clinic on a regular basis. As a result of a randomized selection (where every member of a population has an equal probability of being included in the sample and where all feasible samples of a given size have an equal probability of being chosen), selected participants were assessed individually using a plate form questioner and agreed to participate in this study for three months, starting in July and ending in September 2019.
Women who visited the al-Zahraa teaching hospital’s outpatient clinic, pregnant or not, were asked to provide their verbal agreement. For roughly 10 minutes, each woman was interrogated (Women who declined to participate were not questioned, and the next lady was chosen). Age, mother socioeconomic circumstances, obstetrical history, medical history, and patient complaint are all taken into account in the case history. Patients were taught how to collect urine samples in a sterile urine container under aseptic circumstances and then send them for a general urine examination. The sample was then given a name, a number, and was quickly taken to the lab for additional analysis.
Data of this study were statistically analyzed using IBM SPSS version 22.0 and descriptive statistic was used to summaries the data, like tables, figures, and measures of central tendency. Analytic statistics were used to compare between the variables. Chi-square (x2) was used, significance was assumed at p ≤ 0.05.
The Ethical Committee of Wasit University’s College of Medicine examined the study protocol and approved it.
In this study the prevalence of bacteriuria in women was found to be 13.3%, in pregnant women 16.7% and in non-pregnant women 10%. Asymptomatic bacteriuria in all women was 5/60 cases 8.3%. This indicates that about 16.7% of pregnant women are at risk of development of acute episode of UTI during pregnancy if they are not properly treated [17, 18].
In this study the prevalence of bacteriuria in women was found to be 13.3% (8/60), in pregnant women 16.7% (5/30), and in non-pregnant women 10% (3/30). Asymptomatic bacteriuria in all women was 8.3% (5/60), in pregnant women was 11.7% (4/30), and in non-pregnant women was 5% (2/30). This indicates that about 16.7% of pregnant women are at risk of development of acute episode of UTI during pregnancy if they are not properly treated. These findings are similar to that of Uncu who reported the prevalence of asymptomatic bacteriuria in pregnant women 9.3% [19]. In a study performed in turkey, the prevalence of asymptomatic bacteriuria was reported to be 8.1% [20]. The results of the present study found significantly high relation between age and bacteriuria (p = 0.00) (Table 1) and revealed that the bacteriuria in women was commonest in the age group 25–30 years 62.5%, and these result agreed with study by Buzayan in Libya [21], but contrast with study in Yemen that observed the bacteriuria was more in the age group 15–24 years 53.7% [22]. The difference may be due to social factors such as early age of marriage and sexual activity. There is no significant relationship between level of education and bacteriuria (p = 0.147) (Table 2), the prevalence of bacteriuria was 30.8% in illiterate, 18.5% in primary, 11.1% in secondary and 5.7% in university level of education However, as the level of education increases there is decrease in bacteriuria among women and these findings are similar with Samad [23]. The prevalence of bacteriuria was 14.7% in married women, and 8% in unmarried women, differences are founded apparently but no statistical difference (p = 0.562) (Table 2), while Krcmery et al., showed that the risk factors for bacteriuria in women include sexual intercourse and having a marital history [24] (Table 3). The bacteriuria in the pregnant women was observed more in the third trimester 21.4% than in the first trimester 6.3%, and second trimester 20%. But no significant (p = 0.423) (Table 4). Similar with Haddad who found that the bacteriuria was more in the third trimester 48.8% [22]. In contrast Buzayan [21], in this study the most frequent isolates were
Bacteriuria | Cases with Bacteriuria | Cases without Bacteriuria | Total | |||
---|---|---|---|---|---|---|
Age / year | NO | % | NO | % | NO | % |
X2 = 13.744 df = 4 p = 0.0001 S | ||||||
18–24 | 1 | 18.75 | 8 | 15.3 | 9 | 15.8 |
25–30 | 5 | 62.5 | 11 | 22.1 | 16 | 27.5 |
31–36 | 1 | 6.25 | 18 | 34.7 | 19 | 30.8 |
37–42 | 1 | 12.5 | 10 | 18.3 | 11 | 17.6 |
43–48 | 0 | 0 | 5 | 9.6 | 5 | 8.3 |
Total | 8 | 13.3 | 52 | 86.7 | 60 | 100 |
The distribution of cases of bacteriuria according to the age of the studied groups.
Level of Education | Cases with Bacteriuria | Cases without Bacteriuria | Total | |||
---|---|---|---|---|---|---|
NO | % | NO | % | NO | % | |
X2 = 5.999 df = 3 p = 0.147 N.S. | ||||||
Illiterate | 2 | 30.8 | 5 | 69.2 | 7 | 10.8 |
Primary | 3 | 18.5 | 11 | 81.5 | 14 | 22.5 |
Secondary | 2 | 11.1 | 20 | 88.9 | 22 | 37.5 |
University | 1 | 5.7 | 16 | 94.3 | 17 | 29.2 |
Marital status | X2 = 0.304 df = 1 p = 0.562 N.S. | |||||
Married | 7 | 14.7 | 40 | 85.3 | 47 | 100 |
Un married | 1 | 8 | 12 | 92 | 13 | 100 |
Total | 8 | 13.3% | 52 | 86.7% | 60 | 100% |
The distribution of cases of bacteriuria in the studied population according to their education level, marital status and UTI.
Bacteriuria | Symptomatic Bacteriuria | Asymptomatic Bacteriuria | Cases without Bacteriuria | Total | ||||
---|---|---|---|---|---|---|---|---|
NO | % | NO | % | NO | % | NO | % | |
Pregnancy | X2 = 1.754 df = 2 p = 0.416 N.S. | |||||||
Pregnant | 1 | 3.3 | 4 | 13.3 | 25 | 83.4 | 30 | 100 |
Non Pregnant | 2 | 6.7 | 1 | 3.3 | 17 | 90 | 30 | 100 |
Total | 3 | 5 | 5 | 8.3 | 52 | 86.7 | 60 | 100 |
The distribution of cases of bacteriuria in relation to the pregnancy and UTI conditions.
Bacteriuria | Cases with Bacteriuria | Cases without Bacteriuria | Total | |||
---|---|---|---|---|---|---|
NO | % | NO | % | NO | % | |
Pregnancy Trimester | X2 = 1.719 df = 2 p = 0.423 N.S. | |||||
First Trimester | 1 | 6.3 | 15 | 93.7 | 16 | 26.7 |
Second Trimester | 6 | 20 | 24 | 80 | 30 | 50 |
Third Trimester | 3 | 21.4 | 11 | 78.6 | 14 | 23.3 |
Total | 10 | 16.7 | 50 | 83.3 | 60 | 100 |
The distribution of cases of bacteriuria in relation to the pregnancy age and UTI.
The percentage of isolated bacteria responsible for bacteriuria.
The results of this work indirectly supported the hypothesis of an association of bacteriuria with age and gravidity. In addition, UTI appears to be multifactorial. A screening for bacteriuria in women especially pregnant women must be done to discover the infected cases, which would allow early treatment to avoid the complications.
The most prevalent risk factors for UTI during pregnancy were poor personal cleanliness, a history of UTI, diabetes mellitus, and anemia. The study recommends training in personal hygiene and health education about the type and frequency of changes in underwear, the number of showers per week, the use of soap, and the use of water to wash genitalia, genital dries, the frequency of micturition, precoital washing, postictal washing, and precoital micturition.
I would like to express my gratitude to the O&G seniors at the outpatient’s clinic in the Al Zahraa teaching hospital for their great assistance in a achieving this research, along with al zahraa teaching hospital internal laboratory staff for their role in conducting GUE and urine culture for each participant in this study.
Handling of power loads onto divertor target plates is one of the most critical problems by the realization of a nuclear fusion reactor. The divertor configuration foreseen for ITER (International Thermonuclear Experimental Reactor) has been designed on the basis of present knowledge on physics and is currently available through most advanced engineering technology. It is presumed to handle a total heat load up to 100 MW, which is, however, expected to be reached during the DT (Deuterium-Tritium) plasma phase [1]. In devices beyond ITER, for example, DEMO (Demonstration Power Station), even much higher heat fluxes into the divertor volume are expected. Therefore, up to 90% of power, coming out of the confinement region, has to be removed before the plasma contacts the divertor plates to guarantee a long enough lifetime of the targets [2]. One of the most attractive ways to reach this is the realization of the state where the plasma is detached from the plates, and the energy is mostly dissipated through the radiation from impure particles in the whole divertor volume. The understanding of the detachment mechanisms and searching for possibilities to reliably control the strongly radiating divertor plasma, being simultaneously compatible with the confinement requirements for the plasma core, is one of the most important issues for fusion studies.
Although axis-symmetric tokamaks are presently the most advanced concept for the realization of the magnetic fusion, studies of the detachment in helical devices [3, 4] are also of high interest and importance for the reactor design. Because of inherently nonaxisymmetric magnetic configurations, the magnetic field topology in heliotrons has unique features, in particular, the existence of magnetic islands and stochasticity of field lines. The magnetic field in helical systems is completely generated by currents in external coils. Therefore, the field topology and its effects on the plasma transport and, in particular, on the plasma detachment conditions and characteristics can be studied by varying the magnetic structure in a wide range. Moreover, such investigations are also useful for tokamak devices, where recently resonant magnetic perturbations (RMP) have been introduced to mitigate excessive divertor power load [5, 6]. Due to RMP, the magnetic field in tokamaks exhibits similar structure as in helical devices, that is, with the presence of magnetic islands and stochastic field lines. Thus, the understanding of detachment features in heliotrons is, therefore, of general interest for magnetic fusion program.
The structure of the present chapter is as follows. In next section, we briefly review the features and main differences in the detachment phenomena in tokamaks and helical devices. Experimental observations on the detached divertor plasmas in LHD without and with the application of RMP are presented. The RMP generates a broad magnetic island embedded in the intrinsic edge stochastic layer, which significantly influences features such as the impurity radiation, divertor foot prints, and detachment stability. The impacts on the core plasma transport characteristics during the detached discharge phase are also analyzed here. In Section 3, an interpretation of the detachment phenomena and features of detached plasmas based on the edge plasma energy balance is presented. In Section 4, different mechanisms of nonlinear oscillations during the detachment onset both in helical devices and in tokamaks are discussed. Conclusions are summarized in Section 5.
By rising the plasma density in tokamaks, the plasma in the scrape-off layer (SOL) and divertor goes through several qualitatively different “regimes” [7]. At a low density level, neutral particles, appearing by the recombination of electrons and ions on the divertor target plates, escape freely into the confined plasma volume. Here, these so-called recycling neutrals are ionized and charged species generated diffuse across the magnetic field back into the SOL. Such a particle convection effectively transports heat coming from the plasma core, and the temperatures of the plasma components vary weakly along the magnetic field in the SOL. This regime is referred as either the sheath-limited one or as that of a weak recycling.
With the increasing plasma density, the fraction of recycling neutrals ionized in the vicinity of the targets is growing up. Therefore, beyond the recycling zone, the plasma convection becomes relatively weaker. As a result, a significant parallel temperature gradient develops in the main part of the SOL and the energy toward the targets is transported predominantly by the heat conduction. This regime is called as the conduction limited or a high recycling one. On the one hand, due to the strong temperature dependence of the parallel heat conductivity,
Contrarily to tokamaks in helical devices, such as LHD and W7-AS, it has been found that the SOL and divertor plasma characteristics do not show such strong nonlinear variation with
Nonetheless, experimental observations demonstrate that in the LHD impurity, radiation plays an important role for the divertor plasma cooling, detachment onset, and stability conditions. Here, however, the main radiation source is not located in the divertor legs but in the stochastic layer. Figure 1 shows the tomographic reconstruction of carbon impurity emission in the edge stochastic layer of LHD just before the detachment transition, as well as the magnetic field line connection length (LC) [15]. Although, the emission of low charge state, CII (C1+), is distributed along divertor leg and the very periphery of the stochastic layer, that from the higher charge state, CIV (C3+), being the main radiating species [16], comes from the stochastic layer only.
The pattern of the connection length LC in the edge stochastic layer of LHD (a); the tomographic reconstruction of the emission from carbon ions CII (514 nm) (b) and CIV (466 nm) (c), recorded just before the detachment onset, at line averaged plasma density
In the LHD, studies on the divertor detachment are performed by seeding impurities deliberately [17, 18, 19] and by applying RMP from special coils [20, 21, 22]. In this chapter, we focus on the detachment with the RMP application, which is a unique feature of the LHD.
The large helical device, LHD, is a heliotron-type fusion machine, in which the magnetic field is produced by superconducting coils with poloidal and toroidal winding numbers
Top view of the LHD torus with the position of divertor probe arrays at the inboard, indicated by numbers and letters “L”& “R” (a); LC distribution in the edge region of LHD, without (upper half) and with (lower half) RMP application (b). The right and left legs, indicated in the figure, are connected to L and R divertor arrays, respectively.
Figure 3 shows the time evolution of several plasma parameters in discharges with and without RMP where the density ramp up was performed without auxiliary impurity seeding, and the edge radiation was coming mainly from carbon impurity sputtered from the divertor target plates. On the one hand, without RMP (blue lines), the growth of the density leads to a sudden increase of the radiated power, see Figure 3(b), and, finally, to the radiation collapse of the whole plasma. On the other hand, with the RMP application (red lines), the radiated power is saturated at a higher level and the state with the plasma detached from the divertor targets is sustained during the whole later phase of the discharge. This is demonstrated in Figure 3(a) by the evolution of the heat load onto the divertor target. The strong cooling of the edge plasma by impurity radiation leads to the decrease of the plasma column effective radius a99 displayed in Figure 3(d).
Time evolution of plasma parameters in the LHD density ramp-up discharges, with (red) and without (blue) the RMP application: The power load onto divertor targets measured by probes (a), the radiated power measured by AXUV (b), line averaged density (c), and the effective plasma minor radius a99 defined as that of the flux surface, containing 99% of the total plasma energy (d).
Figure 4 shows the radial profiles of the electron temperature
Radial profiles of the plasma parameters in the LHD edge region: electron temperature (a, d, g), density (b, e, h), and pressure (c, f, i); the panels (a–f) correspond to discharges with RMP, (g–i)—without RMP. The region of the Te flattening caused by the magnetic island is indicated by yellow patch [
The edge impurity radiation profiles are estimated using the
The calculated LC distribution in the outboard edge region (upper panels); time evolution of the carbon radiation estimated from Te and ne profiles as shown in
Radiation profile measurements have been performed to capture the change of the global structure of impurity emission due to RMP and are compared with numerical transport simulations with the code EMC3-EIRENE [20, 21, 22]. Figure 6 shows the calculated impurity radiation distribution, with and without RMP, and the radiation profile measured by the AXUV diagnostics [20]. Without the RMP application, the impurity radiation is enhanced at the inboard as it is demonstrated in Figure 6(a). The line integrated radiation profile found both in the measurements and in simulations are shown in the right panel. Both profiles have maxima at the center channels, which pass through the enhanced radiation at the inboard location. With the RMP, the peak of the radiation moves to the bottom of the plasma, where the X-point of the m/n = 1/1 island is located (note that the toroidal angle positions of the cross sections are different in Figures 2(b) and 6). The simulation also shows a peak at the bottom channel in accordance with the measurement. The measurements by imaging bolometer also indicate enhanced radiation around X-point in agreement with the numerical simulation [21].
Carbon impurity radiation distribution calculated by EMC3-EIRENE at poloidal cross section, together with line-integrated profile of the simulation and measurements by AXUV, on the right panel, without (a) and with (b) RMP [
The impact of RMP on the impurity emission intensity was also investigated in the VUV range with the diagnostic equipment [22], viewing the entire plasma toroidal cross section. Density dependence of the radiated power measured by the resistive bolometer, together with emissions from different charge states, CIII (C2+), CIV (C3+), CV (C4+), and CVI (C5+), measured with the spectrometer [27] is plotted in Figure 7. Here, the plasma density is normalized to the density limit in helical devices, nsudo [28]. It is seen that without RMP, the radiated power shows rapid increase around the density limit, that is,
Density dependence of the radiated power measured by the bolometer (a), the emissivity of CIII (b), CIV (c), CV (d), and CVI (e) species measured by VUV spectrometer without (triangles) and with (circles) RMP. The density is normalized to the density limit in helical devices, nsudo [
The results above clearly show the difference of edge impurity radiation and transport with and without RMP. This is of high importance for the detachment stabilization in the former situation. The mechanism of the stabilization of the radiation layer is under investigation by taking into account the magnetic geometry, the particle, and the energy transport, both parallel and perpendicular to the field lines within and out of the magnetic island. Similar observations of the detached plasma stabilization with large island were also found in W7-AS [29]. The recent results on the successful detachment control in W7-X with the island divertor also suggest an important role of the edge magnetic island for the detached plasma stability [30].
The toroidal variation of the particle fluxes onto divertor plates with RMP has been investigated with Langmuir probe array installed around the mid-plane of the targets at the inboard side [17, 31]. It has been found that the time evolution of the divertor particle flux exhibits substantial difference between toroidal locations, that is, some plates are becoming detached earlier than others; at some plates, the flux even increases after detachment [27]. The summary of this behavior is shown in Figure 8, where the divertor particle flux normalized to its value without RMP is plotted for different toroidal sections. In the attached case, there is an n = 1 mode structure for both left (L) and right (R) divertor arrays, which are connected to the left and right legs, respectively, as indicated in Figure 2. In the detached phase, the n = 1 structure remains, but the toroidal phase is shifted by one section. The relation between the divertor flux and LC profiles is presented in Figure 9 for several toroidal cross sections [27]. At the section 6L (Figure 9(a) and (b)), a bundle of flux tubes of 6.5 mm width is connected to the divertor plate. By applying RMP, the footprint shifts toward the right side with increased LC. The measured particle flux increases in the absolute values due to the longer LC, as seen also in Figure 9(a). The flux profile becomes more asymmetric with respect to the central peak, being increased at the right side, which reflects the right shift of the LC footprint. On the other hand, the 2R plate shows decrease of the particle flux with the RMP application, as seen in Figure 9(c). This is interpreted by the decrease in LC, as shown in the figure, where the long LC bundle at the central region almost disappears with RMP, and thus, the particle flux decreases as well. These results show that, to a certain extent, the particle transport is well correlated with the LC distribution calculated in the vacuum approximation, i.e., without a plasma response to RMP, and thus can be controlled by the RMP application in the attached phase. In the detached phase, the particle flux both at 6L and 2R decreases in the entire region with respect to the case without RMP, as shown in Figure 9(b) and (d).
The toroidal distributions of the particle flux onto divertor targets with RMP normalized by the values without RMP on attached (a) and detached (b) discharge phases. Red circles correspond to the left divertor and blue diamonds to the right divertor arrays, as it is indicated in
LC (solid lines) and divertor particle flux (dashed lines with circles) profiles along the divertor probe pins, with (red) and without (black) RMP. (a and b) 6L, (c and d) 2R, and (e and f) 2L toroidal section, respectively [
In Figure 9(e) and (f), the observations in section 2L are presented. By applying RMP, the particle flux becomes smaller in the attached phase with respect to the reference case without RMP. The flux, however, increases at the detached phase, as shown in Figure 9(f). At this plate, the fraction of long flux tubes with LC > 100 m decreases, but those with LC ∼ 30 m increases with RMP. The reduction of the flux at the attached phase may be due to the reduction of the contribution from the tubes with LC > 100 m. On the other hand, in the detached phase, the increases of the flux could be attributed to the change of the particle transport channel from long, LC > 100 m, to the medium, LC ∼ 30 m, flux tubes. This effect has to be investigated by analyzing in detail the relation between the magnetic field structure and the ionization front. It has to be taken into account that there is a significant plasma response to the RMP, which is different in the attached and detached phases, as mentioned above.
During the detached phase, there are large oscillation in both divertor particle flux and radiation. Figure 10 presents the time traces of the particle flux to the divertor targets and of the radiation losses measured by AXUV during the detached phase, where oscillation with 60–90 Hz is visible. The particle flux and radiation are oscillating in phase. Similar behavior was also observed in the particle flux to the first wall [32]. The mechanism of the oscillation is discussed later in this chapter.
Time traces of the radiation losses, measured by the AXUV (green line), and that of the particle flux to divertor targets (red and blue lines) during detached phase with RMP.
The parameter space of a stable discharge performance with the RMP and the plasma detached from the divertor targets has been investigated by varying the RMP amplitude and location of its resonance layer. Figure 11(a) shows the density dependence of the radiated power at different RMP amplitudes quantified by the ratio
The radiated power as a function of density for different RMP amplitudes (a) and density at the detachment transition (circles) and radiation collapse (triangles) as a function of RMP amplitude (b).
The radial position of the resonance layer of the m/n = 1/1 RMP was scanned by changing the rotational transform
Radial profiles of Te for different profiles of the rotational transform. Configurations differ by the position of the magnetic axis, Rax. The stable detachment was realized for Rax = 3.85 and 3.90 m so far.
The findings discussed above are summarized in Figure 13, where the radial location of the island is represented by the distance between the island X-point and the LCFS [12]. Here, the results from W7-AS are also incorporated. The operation spaces for two devices are not overlapping, which means that probably some hidden parameters important for the detachment stabilization are still missed. Nevertheless, it is seen that for stable sustainment of a detached plasma, there is a threshold value of
The operation space in the plane
The compatibility of a stable detached plasma with a good performance in the plasma core is an important issue for a fusion reactor. Temporal evolution of the radial profiles of
Radial profiles of (a–c) electron pressure, (d–f) ne, and (g–i) Te, with (red) and without (black) RMP, for different densities,
Density dependence of energy confinement time,
The global parameters are significantly affected by the change in the plasma volume caused by the RMP application. In order to study the local plasma transport characteristics, a core plasma energy transport has been analyzed with the 1-D transport code TASK3D [33]. This code calculates the heating source profile, in the present case by the NBI, by taking into account the beam slowing down and solves a heat conduction equation with
Figure 16 shows the resulting NBI power deposition profiles and effective heat conductivity,
Radial profiles of (a–c)
The most visible approach to understand the detachment mechanisms is to analyze the power balance at the plasma edge by applying the concept of dissipative structures [36]. The power transported from the plasma core by the plasma heat conduction is lost from the edge region mostly through two channels: (i) the plasma particle outflow through the separatrix and (ii) the radiation of light impurities such as carbon sputtered from the divertor target plates.
On the one hand, the density of the former channel
Temperature dependence for the energy loss channels from the plasma edge with the plasma conduction and convection through the separatrix,
Both
In a steady state, the energy loss from the plasma edge has to be balanced by the heat transfer from the plasma core, with the density
Temperature dependence for the density of the energy loss from the plasma edge
For the intermediary level of the density,
As it was discussed in the first part of the present chapter, there is a significant difference between the detachment scenario in LHD without and with RMP. In the former case, one needs very fine tuning of the radiation level by gas puffing of fuel or impurity, and detachment onset may lead to a total radiation collapse of the discharge. Unlikely, with RMP after the transition to the detached state, the plasma density can be increased further, with corresponding growth of the radiated power and without a significant deterioration of the discharge performance. Finally, a radiation collapse occurs roughly at the same plasma density as without RMP.
Interestingly, that by the detachment onset with RMP, there is some density range where nonlinear oscillations of high amplitude and relatively low frequency of
Here, we consider two new mechanisms. The first one is relevant for LHD, with plasma of relatively low density in its divertor legs. In such a situation, by approaching to the critical density, the plasma detaches practically directly from the periphery of the edge stochastic layer. This reminds the phenomenon of radial detachment in limiter tokamaks such as TFTR and TEXTOR. The threshold conditions for radial detachment have been analyzed in [41].
The second mechanism is pertinent for the case of tokamaks with divertors like JET, ASDEX-U, DII-D, operating before detachment in the regime of strong plasma recycling on the target plates [7].
In the simplest case, the behavior of the plasma temperature
where
For carbon impurity, dominating the radiation losses from the plasma edge in LHD,
Subsequently, we multiply Eq. (1) with
where
In Figure 19, the rhs of Eq. (4) is displayed for
Dependence of time derivative of the plasma temperature at the outer boundary of the stochastic layer, xs, the rhs of
According to Figure 19, if a critical plasma density of
For the stationary impurity concentration, we assume
The time evolution of the impurity radiation level
One can see that the frequency of these oscillations is of
By concluding this section, we discuss qualitatively possible causes for the difference in the behavior of the detached plasma in LHD without and with RMP, respectively, an unstoppable penetration of cold plasma into the core, leading to the radiation collapse, and the existence of the plasma density range where the radiation layer is stably confined at the plasma edge. As it has been demonstrated in [42], the mechanisms both of plasma heating and heat transfer through the plasma are of the importance for the discharge behavior by achieving the critical density. In ohmically heated discharges in the tokamak TEXTOR, where the plasma current was maintained at a preprogrammed level, a radial detachment was stopped by the increase in the density of the heat flux from the hot plasma core due to decreasing minor radius of the current carrying plasma column. If, however, the main heating is predominantly supplied from other sources such as NBI, this stabilization mechanism is ineffective and, as calculations in [42] have shown, a radiation collapse occurs, similar as this happens in LHD without RMP.
What occurs as a detachment set is determined by the competition between the decay of the impurity concentration in the plasma, characterized by the time
In a stationary state, the plasma parameters, such as electron density
A schematic view of the charged and neutral particle flows in the recycling zone (RZ) in vicinity of a divertor target plate;
Here,
In addition to Eq. (6), the particle balance in the RZ has to be fulfilled in a stationary state:
where
where
The width
The boundary conditions presume that atoms escape out of the plasma layer with their thermal velocity. With constant
with
For fixed
The
The density of the charged particle influx into the RZ,
where
In a stationary state,
To analyze the stability of stationary states, we assume as usually that there is a spontaneous small deviation from such a state, i.e.,
where
It is of interest to consider how
For large enough
Thus, as a function of
The case of the intermediate
Schematic view of the limit cycle oscillations around an unstable steady state at
Time evolution of the plasma flux density onto the target,
Plasma detachment from divertor targets is an important and very interesting phenomenon in fusion devices including helical systems and tokamaks. On the one hand, it can lead to the deterioration of the plasma performance and even to the total collapse of the discharge. On the other hand, detachment, if it is controlled and stable can be useful for the reduction of the heat power losses to the target plates and even may lead to peaking of the pressure profiles in the plasma core that manifests in a confinement improvement. Resonant magnetic perturbations providing a broad enough magnetic island close to the separatrix has proven to be an effective method to control detachment in LHD.
Often at the onset of the detachment, large nonlinear oscillations of relatively low frequency can be observed in different plasma parameters, such as radiated power and ion saturation current to the target plates. Two models of such self-sustained oscillations are proposed. The first one is relevant to the radial detachment in LHD with divertor legs of low plasma density and transparent for neutrals. The second model offers an explanation for phenomena in tokamaks observed at the transition from strong recycling to plasma detachment at divertor targets.
The authors are grateful for the fruitful discussions with Prof. S. Masuzaki, Prof. S. Morita, Dr Y. Narushima, Prof. N. Ohno, Prof. B.J. Peterson, Prof. R. Sakamoto, Dr R. Seki, Dr H. Tanaka, Dr T. Tokuzawa, Prof. K.Y. Watanabe, Prof. H. Yamada, Dr I. Yamada, Prof. M. Yokoyama, Dr. J.W. Ahn, Dr Y. Feng, Prof. K. Ida, Prof. K. Itoh, Prof. S. Kajita, Dr G. Kawamura, Prof. T. Morisaki, Dr K. Mukai, Dr K. Nagaoka, Prof. M. Osakabe, Dr H. Takahashi, and Prof. K. Tanaka. The authors also thank the LHD experimental group for the excellent operation of LHD. The work has been financially supported by JSPS KAKENHI with grant numbers JP16H04622 and JP19H01878 and NIFS budget code ULPP026.
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