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EN
Measurement of the gross alpha and beta activity concentrations in various matrices is suitable as a preliminary screening procedure to determine whether further analysis related to specific radionuclide is necessary. In Serbia, according to current regulations, radioactivity concentrations in drinking water for gross alpha and gross beta should be < 0.5 and < 1.0 Bq L−1, respectively. The generally accepted methods for gross alpha and beta activity analysis of drinking water in different countries are: EPA 900.0 and ISO methods (ISO 9696, water quality – measurement of gross alpha activity in non-saline water – thick source method, and ISO 9697, water quality – measurement of gross beta activity in non-saline water). This paper describes comparison of preparations and measurement gross alpha and beta activity in bottled mineral waters as well as in tap waters in Serbia using two methods: EPA 900.0 with and without ash, and ISO methods. Concentration of total dissolved solids (TDS) in investigated water samples was determined. Based on obtained TDS, certain volume was evaporated. The instrumentation used to count the gross alpha and gross beta activities for both methods is α/β low level proportional counter Thermo Eberline FHT 770 T.
EN
In the Upper Silesian Coal Basin highly mineralized mine waters are pumped into numerous sedimentary ponds before discharge to the Vistula river. They contain elevated concentrations of natural radionuclides (mainly radium). In ponds, some fraction of radionuclides is removed from the water column by adsorption on settling particles, precipitation or co-precipitation, thus increasing radioactivity levels in the deposits. Due to fluctuations of water level and wind action, fine fraction of the deposited material can be distributed in the vicinity of ponds. Three ponds have been selected for survey of the gamma equivalent dose: Brzeszcze, Kaniów, and Rontok Duży. The lowest dose rates, below 0.33 miSv/h, were detected in the area of the Brzeszcze pond. The highest values were measured over the sediments of the Kaniow pond (8.37 miSv/h), being 30 times higher than the dose rate received by population in Poland from natural sources.
3
Content available remote The dose of gamma radiation from building materials and soil
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EN
The radioactivity of some structural building materials, rows, binders, and final construction products, originating from Serbia or imported from other countries, was investigated in the current study by using the standard HPGe gamma spectrometry. The absorbed dose in the air was computed by the method of buildup factors for models of the room with the walls of concrete, gas-concrete, brick and stone. Using the conversion coefficients obtained by interpolation of the International Commission on Radiobiological Protection (ICRP) equivalent doses for isotropic irradiation, the corresponding average indoor effective dose from the radiation of building materials of 0.24 mSv·y−1 was determined. The outdoor dose of 0.047 mSv·y−1 was estimated on the basis of values of the specific absorbed dose rates calculated for the radiation of the series of 238U, 232Th and 40K from the ground and covering materials. The literature values of the effective dose conversion coefficients for ground geometry were applied as well as the published data for content of the radionuclides in the soil.
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EN
The concentration of radon and its decay products in the boundary layer of the atmosphere varies and depends on many factors. One of the main factors leading to the variability of equilibrium equivalent concentration (EEC) of radon is the dynamic behavior of the atmosphere. Describing the behavior of radon concentration and EEC in the atmosphere is important for the estimation of natural human exposition (this was our original goal). The National Institute for Nuclear, Chemical and Biological Protection (SÚJCHBO, v.v.i.) has been investigating the characteristics of radon decay products in the boundary layer of the atmosphere since 1985. The measurements of EEC were carried out in places with different exhalation of radon from the subsoil. The grab sampling method, as well as continuous measurement, were applied in various areas. The determination of outdoor radon and radon daughter product (RnDP) is not easy due to very low levels of their concentrations: therefore, many methods and devices had to be modified for this type of measurement.
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EN
The radioactivity of some structural building materials, rows, binders, and final construction products, originating from Serbia or imported from other countries, was investigated in the current study by using the standard HPGe gamma spectrometry. The absorbed dose in the air was computed by the method of buildup factors for models of the room with the walls of concrete, gas-concrete, brick and stone. Using the conversion coefficients obtained by interpolation of the International Commission on Radiobiological Protection (ICRP) equivalent doses for isotropic irradiation, the corresponding average indoor effective dose from the radiation of building materials of 0.24 mSv·y−1 was determined. The outdoor dose of 0.047 mSv·y−1 was estimated on the basis of values of the specific absorbed dose rates calculated for the radiation of the series of 238U, 232Th and 40K from the ground and covering materials. The literature values of the effective dose conversion coefficients for ground geometry were applied as well as the published data for content of the radionuclides in the soil.
EN
In this paper we describe the first measurements of 210Pb concentrations in sediments, performed in the Institute of Physics, Silesian University of Technology, Gliwice. The reliability of our method has been tested by the 210Pb measurements in the sediments of Lake Gościąż. The reasons for the non-monotonic profile of 210Pb in these sediments have been discussed. We also report and discuss the 210Pb measurements in the sediments formed in front of the Skeidarar glacier (Iceland).
PL
W Polsce systematyczne badania promieniotwórczości naturalnej w surowcach i materiałach budowlanych prowadzone są od 1980 r. W oparciu o wyniki badań prowadzonych przez Centralne Laboratorium Ochrony Radiologicznej (CLOR) i ponad 30 innych laboratoriów w naszym kraju powstała ogólnopolska baza danych z wynikami promieniotwórczości naturalnej. Baza ta jest nadzorowana przez CLOR i zawiera wyniki badań dla ponad 42 000 analizowanych próbek od 1980 r. do chwili obecnej. W artykule przedstawiono wyniki badań radioaktywności wybranych surowców i materiałów budowlanych, oceniono możliwość zastosowania ich w budownictwie mieszkaniowym oraz oceniono narażenie osób na promieniowanie jonizujące wynikające z zastosowania tych materiałów w budownictwie mieszkaniowym.
EN
The systematic research of the natural radioactivity of raw and building materials has been performed in Poland since 1980. Based on the results of these studies, carried out both by the Central Laboratory for Radiological Protection (CLOR) and more than 30 other research laboratories in our country, the national database of measurements of natural radioactivity has been set up. The database is supervised by the CLOR and contains the results of the measurements for more than 42 000 analysed samples since 1980 up to now. In this paper shows results of studies natural radioactivity of the selected raw and building materials, estimated possibility used them in housing and estimated exposure of people on ionization radiation resulting from use these materials in housing.
PL
Węgiel kamienny, jak każdy surowiec mineralny, charakteryzuje się pewną zawartością naturalnych izotopów promieniotwórczych. Ich ilość zależy od ilości i rodzaju zanieczyszczeń zawartych w węglu. Zawartość naturalnych izotopów promieniotwórczych w stałych odpadach ze spalania węgla kamiennego jest jednym z podstawowych parametrów decydujących o możliwościach ich wykorzystania. Wymagania stawiane przez ochronę środowiska i odbiorców węgla kamiennego zmuszają do produkcji sortymentów o ściśle określonych parametrach jakościowych. Spełnienie tych wszystkich wymagań jest możliwe jedynie przy dobrej znajomości parametrów jakościowych węgla stanowiącego nadawę do procesów wzbogacania. Optymalizacja procesu wzbogacania w cieczach ciężkich na podstawie znajomości składu petrograficznego nadawy, a także zależności między składem petrograficznym węgla i składem chemicznym popiołu a interesującą nas właściwością czy składnikiem, daje możliwość uzyskania koncentratów węglowych o właściwościach wymaganych lub zbliżonych do wymaganych przez odbiorców. Zależności między składnikami petrograficznymi węgla i współwystępującą z nimi substancją mineralną (charakteryzowaną składem chemicznym popiołu) a zawartością naturalnych izotopów promieniotwórczych są słabo rozpoznane. Znajomość tych zależności daje możliwość produkcji węgli energetycznych, przyjaznych dla środowiska nie tylko z uwagi na konieczność ograniczania emisji, ale również dzięki temu, że powstające podczas ich spalania odpady, mogą być wykorzystywane do produkcji materiałów budowlanych lub bezpiecznie składowane. Badania wykazały, że zawartość radionuklidów różnicuje się w zależności od klasy ziarnowej węgla (sortymentu). Maksymalne zawartości poszczególnych izotopów są znacznie większe w miałach niż w sortymentach grubych i średnich. W sortymentach grubych i średnich wrasta stężenie radionuklidów wraz ze wzrostem sumarycznej ilości macerałów grupy witrynitu i karbargilitu, w którym substancja mineralna współwystępuje z witrynitem. W sortymentach grubych i średnich stwierdzono regularny wzrost zawartości wszystkich izotopów w miarę wzrostu zawartości popiołu. W przypadku miałów taka korelacja jest wyraźnie widoczna dla izotopu 40K. Zawartość radionuklidów zmienia się również wraz ze wzrostem gęstości węgla. W miarę wzrostu gęstości wydzielonych frakcji zwiększa się zawartość popiołu i stężenia izotopów promieniotwórczych. Maleje zawartość czystych, niezmineralizowanych mikrolitotypów witrynitowych: witrytu, klarytu witrynitowego oraz duroklarytu. Wzrasta natomiast wyraźnie zawartość karbominerytu, głównie karbargilitu (połączenia substancji węglowej z substancją ilastą). Najczęściej są to ziarna witrynitowe i klarytowe przesycone substancja ilastą (zmineralizowany witryt). Wraz ze wzrostem ilości popiołu, karborninerytu i izotopów promieniotwórczych we frakcjach zwiększa się zawartość Si02 i K20. Maleje natomiast zawartość: Fe203 i CaO, Na20, S03 i P205. Wzrasta również zawartość: As i Rb, a obniża się zawartość Co, Cr, Cu, Mn, Ni, Sr i V.
EN
For hard coal, as for any other raw mineral material, some content of natural radioactive isotopes is characteristic. Their quantity depends of quantity and kind of contaminants contained in coal. Content of natural radioactive isotopes in solid waste materials from hard coal combustion is one of basic decisive parameters about possibilities of their utilisation. The demands put up by environmental protection and requirements of hard coal receivers force production of assortments with rigorously defined quality parameters. Fulfilment of all these requirements is possible only under the condition of good knowledge concerning qualitative parameters of coal constituting material fed mechanically for enriching processes. An optimisation of enriching process in heavy liquids on the ground of knowledge concerning fed material petrografical composition, as well as relations between petrografical composition of coal and ash chemical composition and the property or component we are interested in, gives us the possibility of obtaining of coal-extracts with required properties or closed to the properties required by receivers. Relations between petrografical components of coal and coincidental mineral matter (characterised by chemical composition of ash) and content of natural radioactive isotopes are only weakly recognised. The knowledge of these dependencies gives possibility of production of steaming coals, environmentally friendly not only because of necessity of its issue limiting, but also owing to the fact that arising during their combustion waste materials can be used in production of building materials or may be safely dumped. Investigations demonstrated that the content of specific radionuclides differentiates depending of coal grain-size categories. Maximal contents for each of isotopes are considerably greater in fines than in large and average coal sizes. For large and average size grades, concentration of radionuclides increases together with increase of total maceral quantities of group vitrinite and carbargilite, in which mineral matter coincides with vitrinite. For large and average size grades, regular increase of content of all isotopes was ascertained together with increase of ash content. In the case of fines such a correlation is clearly visible for isotope 40K. Radionuclides content also changes together with increase of coal density. As the density of extracted fractions grows larger, the content of ash and concentrations of radioactive isotopes increases. Decreases the content of clear, non-mineralised vitrinite microlitotypes: vitrite, vitrinite clarite and hardening clarite. However, clearly increases significantly content of carbominerite, mostly carbargilite (connections of coal-matter with silty matter). Most often these are the grains of vitrinite and clarite permeated with silty matter (mineralised vitrite). Together with growing quantity of ash, carbominerite and radioactive isotopes, the content of Si02 and K20 in fractions increases. However, decreases content: Fe203 and CaO, Na20, S03 and P205. Increases also content As and Rb, and drops content Co, Cr, Cu, Mn, Ni, Sr and V.
EN
This article presents a comparison of results from the activity measurements of loess samples obtained with two methods in two laboratories. The methods are semiconductor gamma radiation spectrometry and gamma radiation scintillation spectrometry. Various measurement geometries and various sets of radioactivity standards were applied. Samples were collected from two loess profiles, namely Dybawka and Tarnawce. The results of activity measurements for natural radioisotopes of uranium, thorium and potassium obtained in the Gliwice and Gdańsk laboratories are in good agreement. Additionally, the activity of 235U was measured in the analysed samples.
10
Content available Natural radioactivity of wastes
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EN
By-products of the combustion of coal (wastes) are often used for various types of construction (dwellings, roads, etc.). The legal regulations (The Ordinance of the Council of Ministers of 2 January 2007 “On the requirements for the content of natural radioactive isotopes of potassium K-40, radium Ra-226 and thorium Th-228 in raws and materials used in buildings for the residence of people and livestock, as well as in the industrial by-products used in the construction, and the control of the content of the aforementioned isotopes” – Law Gazette no. 4/2007 item 29) are in force in Poland. The regulations permit the possibility of utilization of raws and by-products basing upon the level of the natural radioactivity of the examined raws and materials. The article is a survey of the results obtained during the measurements of many types of raws and building materials for almost 30 years by the network of the laboratories in Poland. It is based upon the results stored in the database of the Central Laboratory for Radiological Protection (CLRP), Warsaw. The article tends to outline the radioactivity of the waste materials with respect to other raws and materials used in the construction industry. The article shows the possibilities for the use of by-products originating in the power stations and heat- and power stations (mainly ashes, slag and hinter) in the construction of dwellings and roads.
EN
This paper reports on the abundance of primordial radionuclides (40K,232K and 238U) in characteristic lithologies from the Sowie Mountains (SW Poland). In situ gamma-ray measurements were conducted at 12 localities hosting exposed augen gneiss, flaser gneiss, granulite, homophanized gneiss, hornblendite, layered gneiss, layered migmatite, migmatic gneiss, mylonitic gneiss and mylonitic granulite. The activity concentration of 40K varied from 180 Bq kg-1 (mylonitic granulite) to 845 Bq kg-1 (layered gneiss). The activity concentrations associated with 228Ac (232Th) varied from 10 Bq kg-1 (mylonitic granulite) to 53 Bq kg-1 (homophanized gneiss), while activity associated with 226Ra (238 U) varied from 9 Bq kg-1 (mylonitic granulite) to 43 Bq kg-1 (layered gneiss). An augen gneiss adjacent to the Intra-Sudetic Fault showed the highest combined Th + U activity (89 Bq kg-1). The average Th/U ratio (3.6) calculated for gneiss outcrops of the Sowie Mountains falls within the range reported for biotite gneiss (3.5-4). Subsurface outcrops from the Walim-Rzeczka underground complex did not give noticeably higher 238U activities. The results obtained forthe Sowie lithologies are compared with those obtained by similar methods for similar rocks as reported in literature sources.
12
Content available remote Implication and hazard of radiation level in the building materials
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EN
The natural radioactivity due to radium, thorium, and potassium in building material samples contribute to the radiation dose received by human beings significantly. It is essential to evaluate the activity levels of these nuclides for the assessment of natural radiation dose. Activity concentrations of the gamma emitting primordial radionuclides 232Th, 226Ra, and 40K were measured using high resolution gamma spectrometry technique with high purity germanium (HPGe) detector in building materials: sand, brick, granite, cement and rock, collected from various areas of Gulbarga and Koppal districts. The standard ASTM procedure was followed for the sample preparation. The distribution of radionuclides and variation in activity concentration depend upon the rock formation and the geological properties of the region. The activity of the three radionuclides, 232Th, 226Ra, and 40K, were found to be in the range of 3.1-227.1, 1.6-111, and 23.2-1505 Bq/kg, respectively. The dose related radiological parameters were also calculated for all the samples and the observations show that the activity concentrations of the radionuclides are well within the UNSCEAR limits.
13
Content available remote Geohazards due to technologically enhanced natural radioactive wastes
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EN
Human activities can modify naturally occurring radioactive material (NORM) into technologically enhanced naturally occurring radioactive material (TENORM) as a result of industrial activities. Most of these industries do not intend to work with radioactive material a priori. However, whenever a uranium- or thorium-bearing mineral is exploited, NORM-containing by-products and TENORM-contaminated wastes are created. The industrial use of NORM can result in non-negligible radiation exposure of workers and members of the public, exceeding by far the radiation exposure from nuclear technologies. For decades, millions of tons of NORM have been released into the environment without adequate control or even with the lack of any control. Various technologies have been developed for the control of NORM wastes. The paper discusses the merits and limitations of different NORM-waste management techniques, such as Containment, Immobilization, Dilution/Dispersion, Natural Attenuation, Separation, and - as an alternative - Cleaner Technologies. Each of these methods requires a comprehensive risk-benefitcost analysis.
EN
This paper includes the results of measurements of natural radioactivity in building materials and raw building materials. The dose rate indoors was calculated on the basis of the contents of K-40, Ra-226 and Th-232 in building materials and the results were compared with literature data of measurements (in situ). The standard procedure for qualifying building materials for building houses designed for habitation was used.
PL
W grudniu 2013 roku została opublikowana DYREKTYWA RADY 2013/59/EURATOM, w sposób istotny zmieniająca istniejące obecnie wymagania dotyczące ochrony przed podwyższoną promieniotwórczością naturalną. Nowe wymagania powinny być wdrożone do polskiego prawa do marca 2018 roku. Wprowadzane zmiany mogą w stopniu istotnym wpłynąć na system ochrony radiologicznej funkcjonujący obecnie w podziemnych zakładach górniczych, w szczególności w zakresie gospodarki wodami złożowymi zawierającymi podwyższone stężenia radu. W artykule przedstawiono spodziewane rozwiązania prawne oraz przeanalizowano wynikające z nich skutki dla zakładu górniczego.
EN
In December, 2013 the New Council Directive 2013/59/EURATOM was published which changes substantially currently existing legal requirements concerning protection against enhanced natural radioactivity. The new regulations must be introduced into Members States’ national legal systems till the end of March, 2018. The new regulations may significantly affect radiation protection system being in use in underground coal mines especially in case of management of radium-rich formation water. In the paper, the expected legal solutions have been highlighted and derived consequences for a coal mine analyzed.
EN
The natural radionuclide (238U, 226Ra, 232Th and 40K) contents in soil were determined for three different regions of Bulgaria using high-resolution gamma-ray spectrometric analysis. A comparison of the dynamics of their behavior throughout the years was performed. Bulgaria is a country with intensive uranium mining activities. That is why radiological monitoring of closed uranium mining facilities in different regions of the country are obligatory and of great interest. This work presents results from such investigations made in regions where remediation was necessary. The results have been evaluated according to Bulgarian radionuclide environment contamination legislation.
PL
Zagrożenie radiacyjne pochodzące od sztucznych izotopów promieniotwórczych jest podstawowym obszarem zainteresowania ochrony radiologicznej. Mniejszą uwagą poświęca się zagrożeniu pochodzącemu od naturalnych izotopów promieniotwórczych. Stężenia naturalnych izotopów promieniotwórczych w skorupie ziemskiej zmieniają się w bardzo szerokim zakresie. Eksploatowane surowce mineralne często zawierają takie stężenia naturalnych izotopów, które mogą powodować istotne zagrożenie. Niektóre procesy technologiczne prowadzą do zatę-żania izotopów promieniotwórczych w odpadach lub wyrobach. Rada Komisji Europejskiej opublikowała w 1996 r. Dyrektywę 96/29/EURO-ATOM (Podstawowe limity bezpieczeństwa). Dyrektywa ta, w artykule 40, zobowiązuje kraje członkowskie Unii do zidentyfikowania obszarów działalności człowieka, które mogą prowadzić do wzrostu zagrożenia radiacyjnego związanego z wykonywaniem pracy jak i dla osób postronnych. Dyrektywa ta wymaga również uregulowania prawnego wszelkich działalności związanych z wykorzystywaniem materiałów zawierających naturalne izotopy promieniotwórcze kiedy powodowane przez nie zagrożenie jest istotne. W artykule omówiono istniejącą w tej dziedzinie sytuację w Polsce. Opisano przykład wzrostu zagrożenia radiacyjnego związanego z podwyższonymi stężeniami naturalnych izotopów promieniotwórczych w odpadach powstających przy eksploatacji węgla kamiennego.
EN
The science of radiological protection and international rules regimes has evolved to ensure safety in the use of artificial sources exposure. Less attention has been given to exposures that can occur as a result of the use of naturally radioactive materials. The levels of naturally occurring radioactivity in the minerals that make up the earth's crust vary widely. In some cases, raw materials that are extracted for industrial uses contain natural radionuclides at concentration that can not be disregarded. Additionally, some industrial process can lead to further enhancement of concentration of radioactivity either in the product or in waste materials. The EC Council in 1996 year published the Council Directive 96/297 Euroatom (The EC Basic Safety Standards). This Directive, in Article 40, requires the nation of the EC to identify work activities which can cause, according to presence of enhanced concentration of natural radioactivity, significant increase of exposure of workers or members of the public to radiation risk. The Directive also requires (Article 41) to regulate all uses of materials containing natural radioactivity where the risk can not be disregarded from radiation protection's point of view. The paper talks about situation in this realm in Poland. An example of creating waste with enhanced radioactivity in hard coal industry was described.
PL
W referacie przedstawiono wyniki badań promieniotwórczości naturalnej wybranych surowców odpadowych. Pracze badawcze dotyczyły odpadów z przemysłu górniczego. Były one prowadzone pod kątem możliwości wykorzystania ich w budownictwie.
EN
In the report one introduced findings of the natural radioactivity of chosen waste-raw materials. Research works reffered waste material from the mining industry. They there were driven at an angle of the possibility of using their in the building.
PL
Osady powstające w wyniku współstrącania się baru i radu z wód dołowych bardzo często w chwili powstania zawierają podwyższone, w stosunku do wartości przyjmowanych za średnie w wierzchniej warstwie skorupy ziemskiej, stężenia izotopów radu (226 Ra i 228 Ra). Wraz z upływem czasu, w rezultacie ich rozpadu promieniotwórczego izotopów, w osadach powstają ich nuklidy pochodne. Najistotniejsze z nich, ze względu na wymagania ochrony radiologicznej, to 228Th i 210Pb. Uwzględnienie tych nuklidów w systemie ochrony radiologicznej w podziemnych zakładach górniczych prowadzi do nieznacznego zaostrzenia kryteriów kontroli. Również, konieczność uwzględnienia większej liczby nuklidów komplikuje sam proces oceny zagrożenia radiacyjnego. Wprowadzenie określonych limitów roboczych, wyrażonych jako stężenie promieniotwórcze poszczególnych nuklidów promieniotwórczych może usprawnić sposób prowadzenia kontroli zagrożenia radiacyjnego w podziemnych zakładach górniczych.
EN
Sediments formed as the result of radium and barium co-precipitation from formation waters, at the beginning usually contain radium isotopes (226Ra and 228Ra) at the concentration level higher than in a common rock from surface Earth crust. With time, as the result of radioactive decay, radium nuclides would emerge in such sediments. From radiation protection point of view the most important are 228Th and 210Pb. If these radionuclides are taken into account as a part of the radiation protection system, the underground coal mines have to slightly stringent the control process. Moreover, the necessity of allowing for additional radionuclides makes the system of radiation assessment itself more complicated. Specific working limits, expressed as radioactive concentration of particular radionuclides, may enhance the control process of radiation hazard in underground coal mines.
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With gamma spectrometric method 23 samples of mineral and thermal waters of Bosnia and Herzegovina were analyzed. Activity concentrations of the investigated radionuclides were in the range 12–346 mBq·L−1 for 40K, 1.1–791 mBq·L−1 for 226Ra, 0.2–221 mBq·L−1 for 228Ra, 13–367 mBq·L−1 for 238U, and 0.6–17 mBq·L−1 for 235U. For all investigated radionuclides annual effective dose was estimated. The estimated total annual committed effective dose received by population as a result of ingestion of water was in the range 0.11–2.51 μSv·y−1 for thermal water and in the range 0.11–38.8 μSv·y−1 for mineral water. Measurement of activity concentrations of natural radionuclides in the examined samples was carried out with a gamma-spectrometer with high-purity germanium (HPGe) detector, having a relative efficiency of 70%.
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