Log In Sign up
The largest database of trusted experimental protocols
> Procedures > Therapeutic or Preventive Procedure > Radiation Protection

Radiation Protection

Radiation protection refers to the measures taken to minimize the harmful effects of ionizing radiation exposure.
This includes the use of shielding, protective equipment, and proper handling procedures to safeguard individuals, such as workers and the general public, from the risks associated with radiation exposure.
The goal of radiation protection is to ensure the safe use of radiation in medical, industrial, and research applications while maintaining exposures as low as reasonably achievable.
Effective radiation protection practices help to reduce the incidnce of radiation-induced health effects, such as cancer and genetic damage, and promote the responsible use of radioactive materials.

Most cited protocols related to «Radiation Protection»

1
Scalable NURBS-based Animal Models
Cited 19 times
Using an interactive scaling program developed by Segars et al. (12 ), any NURBS model may be scaled to different sizes and shapes. One or more selected organs may be translated or rotated in any direction; scaled linearly in any direction, uniformly in 3 dimensions, or from the center by a fixed factor; or otherwise modified by the user. Instead of spending months or years creating, performing, and perfecting tedious, slice-by-slice segmentations of individual organs from diagnostic imaging data of various animals, we found this method to be much quicker, resulting in a model series that was more internally consistent. We used this program to develop a series of models representing small, medium, and large animals typically used in preclinical research in nuclear medicine—mice weighing about 25, 30, and 35 g and rats weighing approximately 200, 300, 400, 500, and 600 g. The resulting organ and body masses were designed to follow data found in reference literature. During radiation transport, traditionally hollow organs (e.g., stomach, intestines, heart, and bladder) were treated as a uniform organ, with mass equal to that of the wall plus contents, as defined in the NURBS models. This treatment was thought reasonable, because of uncertainties in the exact location of these small structures. The skeleton similarly was treated as a uniform mixture of bone, cartilage, and marrow; development of a detailed bone model with microstructure representing the individual components was beyond the scope of this project and was thought to include uncertainties similar to or greater than those for hollow organs.
Separate models were made for each size rodent. The modified models were saved, converted to a voxelized format, and used in the geometry and tracking particle transport toolkit (GEANT, version 4) (15 ) to perform radiation transport calculations in the voxel-based representations of the various individual models. Cubic voxels of 0.625 mm were used; models started at 512 × 512 × 512 voxels but were trimmed to sizes that removed empty space around each model, to speed up the Monte Carlo simulations. For most organs, the difference between the MOBY and the ROBY reported and voxel model volumes was about 3%–5%. For small organs, however, the difference was sometimes greater. In the absence of well-established information about these species, the tissue compositions and densities recommended for humans (16 ) were used for the corresponding tissues of the animals. Minor changes were suggested in the recently released revision by the International Commission on Radiological Protection (ICRP) (17 ). However, these changes were not deemed large enough to affect calculations from our established Monte Carlo routines, given all other uncertainties in the data and methods, which may be as much as a factor of 2 or more (18 (link)) whereas variations in tissue densities are of the order of a few percentage points. Discrete starting photon and electron energies of 0.01, 0.015, 0.02, 0.03, 0.05, 0.1, 0.2, 0.5, 1, 1.5, 2, and 4 MeV were simulated in available source regions. Typically 600,000 particle histories were followed in the Monte Carlo simulations, which were implemented on the Vanderbilt multinode computing environment (Advanced Computing Center for Research and Education). SAFs were generated for source and target regions in the models, and then organ DFs were generated, using decay data from the RAdiation Dose Assessment Resource (RADAR) (19 (link)). In most cases, uncertainties in the SAFs were under 2%; in a few cases, the variability of the data was high (some small organs or organ pairs that were significantly separated), and reciprocity rules (14 (link)) and smoothing of noisy data were performed in some cases.
Keenan M.A., Stabin M.G., Segars W.P, & Fernald M.J. (2010). RADAR Realistic Animal Model Series for Dose Assessment. Journal of nuclear medicine : official publication, Society of Nuclear Medicine, 51(3), 471-476.
Publication 2010
Animals Bone Development Bones Cartilage Cuboid Bone Electrons factor A Heart Homo Human Body Intestines Marrow Mice, Laboratory Radiation Radiation Protection Radionuclide Imaging Rattus norvegicus Rodent Skeleton Stomach Syntex adjuvant formulation Tissues Urinary Bladder
2
Automated Bone Scan Lesion Detection
Cited 15 times

Protocol full text hidden due to copyright restrictions

Open the protocol to access the free full text link

Publication 2012
Arm, Upper Bone and Bones Bones Cranium Diagnosis Drainage Leg Males Malignant Neoplasms Neoplasm Metastasis Patients Pelvis Physicians Radiation Protection Radionuclide Imaging Ribs Skeleton Urinary Bladder Urinary Catheter Urine Vertebrae, Lumbar Whole Body Imaging Woman
3
Leukemic Bone Marrow Transplantation
Cited 14 times

Protocol full text hidden due to copyright restrictions

Open the protocol to access the free full text link

Publication 2012
Biological Assay Cells Institutional Animal Care and Use Committees Mice, Inbred C57BL Mus Radiation Protection RRAD protein, human Tail Tissue Donors Veins
4
Radiochemical Synthesis and Characterization of Lu-PSMA
Cited 12 times
PSMA was obtained from ABX GmbH (Radeberg, Germany). To begin, 1 mg DOTA-PSMA was dissolved in 1 ml 0.05 M HCl. Then, 88.50 ± 9.21 μg DOTA-PSMA per 10 μg Lu was added to 1 ml 0.05 M HCl solution containing 42 mg gentisinic acid and 210 mg sodium ascorbate. This mixture was added to carrier-added 177LuCl3, obtained from IDB Holland, and heated for 30 min at 95 °C. Quality control was performed by spotting 1 μl aliquots on TLC (SilicaGel 60, Merck, Darmstadt, Germany) with 0.1 M citric buffer or ITLC-SG plates (ITLC-SG, Varian, Lake Forest, CA, USA) and with 1 M NH4OAc/MeOH (1:1) as solvent. Analysis was performed using a flat-bed scanner (Rita Star, Raytest-Isotopenmessgeräte GmbH, Straubenhardt, Germany). Radiochemical purity was determined by radio HPLC, which was performed using a gradient system. The gradient elution system utilised mobile phase A (deionised H2O containing 0.1 % TFA) and mobile phase B (100 % acetonitrile) and a flow rate of 1.0 ml/min. Starting with 100 % A/0 % B, the gradient was increased to 100 % B over 30 min and then returned to the initial gradient conditions within 5 min. The retention time of free 177Lu was Rt = 2.5 min, whereas for Lu-PSMA it was 13.3 min.
The labelling yield always exceeded 95 % (98.85 ± 1.29 %); therefore, no purification was performed. The radiochemical purity was higher than 98 %. The specific activity of Lu-PSMA was 89.73 ± 13.61 MBq/μg.
The therapy solution was administered by slow intravenous injection over 1 min followed by 1000 ml of NaCl or Ringer. In order to reduce therapy-induced damage to the salivary glands, the patients received ice packs over the parotid and submandibular glands from 30 min prior to and up to 4 h after administration of the Lu-PSMA. All patients were discharged 48 h after therapy according to the rules of the Federal Office for Radiation Protection in Germany (BfS).
Ahmadzadehfar H., Rahbar K., Kürpig S., Bögemann M., Claesener M., Eppard E., Gärtner F., Rogenhofer S., Schäfers M, & Essler M. (2015). Early side effects and first results of radioligand therapy with 177Lu-DKFZ-617 PSMA of castrate-resistant metastatic prostate cancer: a two-centre study. EJNMMI Research, 5, 36.
Full text: Click here
Publication 2015
acetonitrile Acids Aftercare Buffers Citric Acid Forests High-Performance Liquid Chromatographies Lutetium-177 Parotid Gland Patients Radiation Protection Radiopharmaceuticals Retention (Psychology) Salivary Glands Sodium Ascorbate Sodium Chloride Solvents Submandibular Gland tetraxetan Therapeutics Training Programs
5
Occupational Organ Dose Estimation
Cited 12 times
Our objectives were twofold: to derive a set of occupational organ-specific doses for all study participants using individual monitoring data, work history and the evolution of radiation protection policies over time; and to characterize uncertainty in individual dose estimates by creating multiple sets of organ-specific dose estimates for the entire cohort. In this schema, each set reflects multiple sources of uncertainty including possible biases and our interpretations of the uncertainties of data, and our assumptions. We refer to each set of doses derived for the entire group as a single “realization”.
To create the realizations of the cohort dose distribution, we developed a year-by-year probabilistic record of badge dose6 and organ-specific radiation absorbed doses for each participant that accounts for uncertainties shared among individuals or subgroups. Information about each technologist's annual badge dose can be represented by a sample from the probability density function (PDF) that was designed to capture the range and the likelihood of plausible values for the technologist's true annual badge dose given what is known about the population dose distribution and shielding practices in that year, together with individual information on work practices, type of facility where work was performed, and when available, film badge readings. Multiple values of individual annual doses were simulated from the PDFs using Monte Carlo simulation techniques that allowed for within-individual inter-year correlations. These individual annual badge dose values were used to generate estimates of annual organ doses that account for uncertainties in individual apron usage patterns, apron thickness and dose conversion factors. The realizations of cohort member doses derived in this study reflect both uncertainties in reconstructing individual doses and uncertainties that are shared between individuals.
Table 1 summarizes changes in the USRT dosimetry since the 2006 publication (13 (link)) and highlights important attributes of the current dosimetry system. These improvements include newly acquired film badge dose readings, and additional information on work history and practices collected in a 2003–2005 survey and methods and models that allow greater individualization of annual dose estimates. The updated badge dose data and work history information were used to estimate annual population badge dose distributions from 1916–1997. These distributions are dependent on the type of facility in which the technologist worked, e.g., a clinic or physician office and the nature of the employer (civilian or military). The badge dose and work history data were used to develop individual exposure scores, a metric that captures the dependence of the geometric mean (GM) of the annual population badge dose distribution on the frequency of performing specific types of radiologic procedures and the number of hours worked per week. Methods were developed to use exposure scores to individualize badge dose sampling densities for years in which a cohort member was believed to have worked but for which a badge dose reading was not available.
Doses to specific organs are dependent on use of apron protection and shielding. Since publication of the original dosimetry system (13 (link)), we have developed methods that use a combination of literature-based and questionnaire-derived information on individual protection practices and use of shielding according to time period. Conversion from an estimated film badge dose to organ-specific doses utilizes newly developed energy- and period-specific dose conversion coefficients and apron transmission factors (TFs) (14 (link)).
Simon S.L., Preston D.L., Linet M.S., Miller J.S., Sigurdson A.J., Alexander B.H., Kwon D., Yoder R.C., Bhatti P., Little M.P., Rajaraman P., Melo D., Drozdovitch V., Weinstock R.M, & Doody M.M. (2014). Radiation Organ Doses Received in a Nationwide Cohort of U.S. Radiologic Technologists: Methods and Findings. Radiation research, 182(5), 507-528.
Publication 2014
Biological Evolution Film Badge Military Personnel Radiation Radiation Protection Radiometry Transmission, Communicable Disease

Most recents protocols related to «Radiation Protection»

1
Respiratory Airflow and Particle Transport
Figure 3 illustrated the details of boundary conditions in this case. The attached breathing zone in front of the cavity was set as zero-gauge pressure inlet to imitate the ambient environment. The outlet of the airway was set as velocity outlet by dividing the physiological volumetric flow rate with the area of the outlet. International Commission on Radiological Protection (ICRP) publication 66 suggests a tidal volume of 0.244 L with a frequency of 39 per minute for children subjects under light exercise condition. Therefore, the equivalent volumetric flow rate of 9.5 litre per minute (LPM) was employed for light exercise condition. Respiratory conditions are determined by human exercise and physical activity. To consider different physiological conditions, numerical simulations under three levels of inhalation flow rates, representing, respectively, resting (3.1 LPM), light exercise (9.5 LPM), heavy exercise (18.9 LPM) circumstances were performed in this study. For the nasal surface as well as surrounding face, it was assumed to be no-slip, stationary and perfect absorbed when predict particle transport.
Sun Q., Dong J., Zhang Y., Tian L, & Tu J. (2023). Numerical modelling of micron particle inhalation in a realistic nasal airway with pediatric adenoid hypertrophy: A virtual comparison between pre- and postoperative models. Frontiers in Pediatrics, 11, 1083699.
Full text: Click here
Publication 2023
Child Dental Caries Face Light Nose Physical Conditioning, Human physiology Pressure Radiation Protection Respiration Disorders Respiratory Rate Tidal Volume
2
Radiation Dose Optimization in ERCP Procedures

All procedures were performed using CO
2insufflation with the patient in prone or left lateral decubitus position under conscious sedation controlled by an anesthesiologist and a nurse. The study procedures were performed using a floor-mounted Siemens Artis zee multi-purpose (MP) fluoroscopy system (Siemens Healthcare, Erlangen, Germany) or a mobile Siemens Cios Alpha c-arm device (Siemens Healthcare, Erlangen, Germany). Fixed, mobile, and ceiling-mounted radiation shields and personal protective equipment, such as protective aprons, thyroid shields, and leaded eyewear were used during all the procedures. A more detailed description of the imaging protocols and radiation protection tools implemented is provided as supplementary material.
Other data collected for each procedure included patient characteristics (age, height, weight, and body mass index [BMI]), fluoroscopy time, KAP, and air-kerma at reference point (K
a,r). Moreover, the procedural complexity of each ERCP was determined and collected based on the 4-point American Society for Gastrointestinal Endoscopy (ASGE) complexity-grading system
18 (link)
19
. The radiation doses in ERCP and other gastrointestinal endoscopy procedures were compared. ERCPs performed for diagnosis and follow up of PSC included a significantly larger number of single image exposures compared to other ERCPs and were thus categorized separately. The effect of ERCP procedural complexity level and fluoroscopy system on radiation doses was then analyzed.
Kaasalainen T., Pekkarinen A., Kylänpää L., Rainio M., Tenca A., Jokelainen K., Barner-Rasmussen N., Puustinen L., Udd M, & Lindström O. (2023). Occupational radiation dose from gastrointestinal endoscopy procedures with special emphasis on eye lens doses in endoscopic retrograde cholangiopancreatography. Endoscopy International Open, 11(3), E237-E246.
Publication 2023
Anesthesiologist Conscious Sedation Cranioosteoarthropathy Diagnosis Endoscopic Retrograde Cholangiopancreatography Endoscopy, Gastrointestinal Fluoroscopy Index, Body Mass Nurses Patients Radiation Protection Radiotherapy Surgical Procedures, Endoscopic Gastrointestinal Thyroid Gland
3
Calculating Respiratory Deposition of Phi6 Virus
The Phi6 dose inhaled by the experiment subjects was calculated from the particle size-resolved APS data using the assumption of 1.6 viruses per particle and by using a lung deposition model presented by the International Commission on Radiological Protection [29 ]. According to ICRP, the deposition efficiency of different sized particles to the human respiratory system can be estimated using the function curves shown in Fig. 2 [29 ]. These curves describe the fraction (%) of particles, which deposit to the head airways, tracheobronchial, and alveolar region (4) of a human respiratory system as a function of particle size. The total deposition efficiency is the sum of the regional depositions. Mathematical equations for these functions have also been presented by Hinds [30 ] (1999). The impact of using a respirator (FFP2 or FFP3) was also considered. The dose inhaled was calculated as follows: Inhalationdose=∑i=152((1−Respleak)*Vinhaled*(1−Respflt)*ni*1.6*Deff,i)+(Respleak*Vinhaled*ni*1.6*Deff,i) where Respleak is the respirator internal leak, Vinhaled is the inhaled (or sampled) air volume, Respflt is the respirator filtration efficiency, ni is the particle number concentration of the ith size bin and Deff,i is the deposition efficiency of particles of ith size bin. The APS measured particle number concentrations in 52 size bins spaced logarithmically from 0.5 to 20 μm.

Respiratory deposition efficiency of 0.001–10 μm sized particles (ICRP, 1994) [29 ].

Fig. 2
Sanmark E., Kuula J., Laitinen S., Oksanen L.M., Bamford D.H, & Atanasova N.S. (2023). Safe use of PHI6 IN the experimental studies. Heliyon, 9(2), e13565.
Full text: Click here
Publication 2023
Filtration Head Homo sapiens Lung Mechanical Ventilator Radiation Protection Respiratory System Virus
4
Spectrophotometric Determination of SPF
In vitro determination of the SPF via spectrophotometry with integrated sphere was carried out using UV-2000S Labsphere® equipment, in which a sample is positioned on a quartz plate, functioning as a substrate that is ideally transparent in the UV range, with texture and porosity similar to human skin. The literature recommends alternative complementary substrates to meet all these requirements. Surgical tape (TransporeTM, 3M), a polyvinylidene chloride film (Saran Wrap®), and collagen membrane covering the quartz plate for meeting the experimental conditions. The quartz plate was prepared with approximately 50 mg of glycerin to obtain a base line in the equipment. The next step was the deposition of approximately 50 mg of the evaluated NE sample on the plate, covered by the film, spread with the help of a latex fingertip, aiming at obtaining the most uniform and homogeneous layer possible for the equipment reading. This reading was performed at nine different points on the quartz plate. The plate was placed on a metal support, which is taken to the equipment and receives the UV light. The SPF readings were made in triplicates for calculating the mean ± relative standard deviation.
The critical wavelength is a spectrophotometrically-determined value based on spectral absorbance and is used to assess whether a photoprotector offers UVA protection. Because it is a relative value–not an absolute value-of spectral absorbance, it is not considered a sensitive measure, such as SPF or that obtained using Boot’s Star Rating (Table 5). For the analysis, the measured spectral transmittance was converted into spectral absorbance, where the ratio (R) was calculated. The critical wavelength is defined as the first value found when the value of R is > 0.9, that is, the wavelength for which the area under the integrated optical density curve, which starts at 290 nm, is equal to 90% of the integrated area between 290 and 400 nm. Therefore, the value of the critical wavelength is related to the level of protection, in which λc values between 340 and 370 nm indicate intermediate protection against UVA radiation, and values above 370 nm indicate greater protection over a wide spectrum [37 (link)].
Boots Star rating measured the % of UVA that’s been absorbed compared to UVB rays (source), so in a sense it measured the evenness of the UV protection. The closer the UVA/UVB ratio is to 1, the more stars a sunscreen gets. Five stars on the Boots system means that UVA protection achieved more than 90% UVB protection.
Reis-Mansur M.C., Firmino Gomes C.C., Nigro F., Ricci-Júnior E., de Freitas Z.M, & dos Santos E.P. (2023). Nanotechnology as a Tool for Optimizing Topical Photoprotective Formulations Containing Buriti Oil (Mauritia flexuosa) and Dry Aloe vera Extracts: Stability and Cytotoxicity Evaluations. Pharmaceuticals, 16(2), 292.
Full text: Click here
Publication 2023
BaseLine dental cement Collagen Glycerin Homo sapiens Latex Metals polyvinylidene chloride Quartz Radiation Radiation Protection Saran Skin Spectrophotometry Stars, Celestial Surgical Tape Tissue, Membrane Vision
5
Radiation Shielding Protocol and Attenuation Analysis
Cited 2 times
Radiation shielding is based on the principle of attenuation, which is the ability to reduce radiation intensity through photoemission and scattering by a barrier material. When a gamma ray passes through an absorber material of thickness x, an exponential attenuation is observed in the intensity of the gamma radiation depending on the chemical content of this material according to Beer–Lambert’s law [20 (link)]: I=I0e−μx,
where I is the transmitted intensity, Io is the incident intensity, x is the thickness of the absorbent (cm), and μ (cm−1) is the linear attenuation coefficient (LAC).
The half-value layer (HVL) and tenth-value layer (TVL) are defined as the thicknesses required to attenuate the incident photon intensity by factors of 1/2 and 1/10, respectively [21 (link)]: HVL =Ln2LAC,
TVL=Ln10LAC.
The mean free path (MFP) (cm) is the reciprocal of linear attenuation coefficient and denotes the average distance that a photon travels inside the sample without any interactions [1 (link)]. Moreover, MAC denotes the mass attenuation coefficient, which is measured by dividing LAC by the density (ρ) [22 (link)]: MAC =LACρ.
Other important shielding parameters can be derived from the mass attenuation coefficient, such as the effective atomic number (Zeff) and effective electron density (Neff). The Zeff and Neff parameters are fundamental in the field of nuclear radiation protection. Zeff depends on the incident photon energy and is used to characterize the shielding properties of composites in terms of pure elements [23 (link)]. Neff is the number of electrons per unit mass of the composite material measured in electrons/g. Zeff and Neff can be calculated from the following relationships [24 (link)]: Zeff=∑ifiAiμρi∑j fi AjZjμρj,
Neff=NAZeffA,
where fi, Ai, and Zi are the fractional abundance, the mass number, and the atomic number of the i-th constituent element in the composite material. 〈A〉=∑ifiAi is the average atomic mass of the composite material, and NA is Avogadro’s number.
The exposure buildup factor (EBF) is essential for radiation scattering studies and assessing shielding material performance. It is defined as the photon buildup factor in the air after penetration through a shielding material with high-energy photons. The EBFs for mortars were computed using G–P fitting parameters as mentioned in previously published studies, and this was achieved using the equivalent atomic number (Zeq), which is an energy-dependent parameter describing the properties of the investigated mortars in terms of their equivalent elements. Zeq is defined by the following equation [25 (link)]: Zeq=Z1logR2−logR+Z2logR−logR1logR2−logR1,
where R1 and R2 are the ratios (μ/ρ) Compton/(μ/ρ) total, which were obtained for mortar at a specified energy using the WinXCom program, corresponding to elements with atomic numbers Z1 and Z2, respectively. R is the ratio for the mortar at the specific energy, which lies between ratios R1 and R2.
The G–P fitting parameters such as (b, a, Xk, d, and c) were then interpolated using the obtained Zeq values at a specific photon energy according to the interpolation formula [26 ]: C=C1logZ2−logZeq+C2logZeq−logZ1logZ2−logZ1,
where C1 and C2 indicate the G–P fitting parameters obtained from ANSI/ANS-6.4.3, the standard database, for Z1 and Z2, respectively.
The EBF values for the selected mortar samples were calculated in the energy range between 0.015 MeV to 15 MeV assisted by G–P fitting parameters using the following equations [27 (link)]: BE,x=1+b−1K−1 Kx−1 , K≠1,
BE,x=1+b−1x , K=1.
In these equations,
KE,x=cxa+dtanhx/XK−2−tanh−21−tanh−2 for x≤ 40 mfp,
where E is incident photon energy, and x is the mfp.
Alabsy M.T., Gouda M.M., Abbas M.I., Al-Balawi S.M, & El-Khatib A.M. (2023). Enhancing the Gamma-Radiation-Shielding Properties of Gypsum–Lime–Waste Marble Mortars by Incorporating Micro- and Nano-PbO Particles. Materials, 16(4), 1577.
Full text: Click here
Publication 2023
Beer chemical content Electrons Gamma Rays Iodine Radiation Radiation Protection

Top products related to «Radiation Protection»

1
Radimetrics by Bayer
Sourced in Germany
Radimetrics is a precision laboratory equipment designed for accurate measurement and analysis. It utilizes advanced technology to provide reliable and consistent data. The core function of Radimetrics is to enable precise quantification and evaluation of various materials and samples within a controlled laboratory setting.
2
Facscalibur by BD
Sourced in United States, Germany, United Kingdom, China, Canada, Japan, Italy, France, Belgium, Switzerland, Singapore, Uruguay, Australia, Spain, Poland, India, Austria, Denmark, Netherlands, Jersey, Finland, Sweden
The FACSCalibur is a flow cytometry system designed for multi-parameter analysis of cells and other particles. It features a blue (488 nm) and a red (635 nm) laser for excitation of fluorescent dyes. The instrument is capable of detecting forward scatter, side scatter, and up to four fluorescent parameters simultaneously.
3
Sprague dawley rat by Charles River Laboratories
Sourced in United States, China, Germany, Canada, United Kingdom, Japan, France, Italy, Morocco, Hungary, New Caledonia, Montenegro, India
Sprague-Dawley rats are an outbred albino rat strain commonly used in laboratory research. They are characterized by their calm temperament and reliable reproductive performance.
4
Psma 617 by Horiba
Sourced in Germany
PSMA-617 is a radioactive compound used in nuclear medicine imaging and therapy. It specifically targets the prostate-specific membrane antigen (PSMA), which is expressed on the surface of prostate cancer cells. PSMA-617 can be labeled with different radioisotopes, such as gallium-68 or lutetium-177, for diagnostic or therapeutic purposes, respectively.
5
Prism 5 by GraphPad
Sourced in United States, Germany, United Kingdom, Israel, Canada, Austria, Belgium, Poland, Lao People's Democratic Republic, Japan, China, France, Brazil, New Zealand, Switzerland, Sweden, Australia
GraphPad Prism 5 is a data analysis and graphing software. It provides tools for data organization, statistical analysis, and visual representation of results.
6
Rotavapor r 210 by Büchi
Sourced in Switzerland, Germany, India, France
The Rotavapor R-210 is a rotary evaporator designed for efficient solvent removal and concentration of liquid samples. It features a rotating evaporation flask, a heating bath, and a condensing system to facilitate the evaporation process. The core function of the Rotavapor R-210 is to safely and effectively separate volatile components from non-volatile substances through controlled distillation.
7
Alpha 1 4 ld plus christ freeze dryer by Martin Christ
Sourced in Germany
The Alpha 1-4 LD Plus is a freeze dryer manufactured by Martin Christ. It is designed for laboratory-scale lyophilization processes. The core function of the Alpha 1-4 LD Plus is to remove water from samples through the process of sublimation, where frozen water transitions directly from a solid to a gaseous state.
8
X rad 320 by Precision X-Ray
Sourced in United States, Canada
The X-RAD 320 is a radiation therapy device that generates X-rays for medical imaging and treatment purposes. It is capable of producing high-energy X-rays for a variety of applications, including diagnostic imaging, image-guided radiation therapy, and small animal research.
9
Fetal bovine serum (fbs) by Thermo Fisher Scientific
Sourced in United States, China, United Kingdom, Germany, Australia, Japan, Canada, Italy, France, Switzerland, New Zealand, Brazil, Belgium, India, Spain, Israel, Austria, Poland, Ireland, Sweden, Macao, Netherlands, Denmark, Cameroon, Singapore, Portugal, Argentina, Holy See (Vatican City State), Morocco, Uruguay, Mexico, Thailand, Sao Tome and Principe, Hungary, Panama, Hong Kong, Norway, United Arab Emirates, Czechia, Russian Federation, Chile, Moldova, Republic of, Gabon, Palestine, State of, Saudi Arabia, Senegal
Fetal Bovine Serum (FBS) is a cell culture supplement derived from the blood of bovine fetuses. FBS provides a source of proteins, growth factors, and other components that support the growth and maintenance of various cell types in in vitro cell culture applications.

More about "Radiation Protection"

Radiation protection is a critical field that encompasses the measures taken to minimize the harmful effects of ionizing radiation exposure.
This includes the use of shielding, protective equipment, and proper handling procedures to safeguard individuals, such as workers and the general public, from the risks associated with radiation exposure.
The goal of radiation protection is to ensure the safe use of radiation in medical, industrial, and research applications while maintaining exposures as low as reasonably achievable.
Effective radiation protection practices help to reduce the incidence of radiation-induced health effects, such as cancer and genetic damage, and promote the responsible use of radioactive materials.
This field is closely linked to various technologies and techniques, including Radimetrics, FACSCalibur, Sprague-Dawley rats, PSMA-617, GraphPad Prism 5, Rotavapor R-210, Alpha 1-4 LD Plus—Christ freeze dryer, and X-RAD 320.
Radimetrics is a software platform that provides dose tracking and optimization for medical imaging procedures, helping to ensure patient safety and optimize radiation exposure.
FACSCalibur is a flow cytometry instrument used in research and clinical settings to analyze cells and their properties, including those affected by radiation exposure.
Sprague-Dawley rats are a common animal model used in radiation protection research to study the biological effects of ionizing radiation.
PSMA-617 is a radioligand therapy used in the treatment of prostate cancer, which requires careful radiation protection measures to ensure the safe administration and handling of the radioactive material.
GraphPad Prism 5 is a data analysis and graphing software used in radiation protection research to interpret experimental results and visualize data.
The Rotavapor R-210 is a rotary evaporator used in the preparation of radioactive samples, while the Alpha 1-4 LD Plus—Christ freeze dryer is employed in the lyophilization of radioactive materials.
The X-RAD 320 is an x-ray irradiation system used in radiation protection research to study the effects of ionizing radiation on various biological systems.
Ultimately, radiation protection is a multifaceted field that relies on a range of technologies, techniques, and best practices to ensure the safe and responsible use of ionizing radiation in medical, industrial, and research applications.
By understanding these various aspects, researchers and practitioners can better protect individuals and communities from the harmful effects of radiation exposure.