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Ionizing Radiation - Science topic
Explore the latest questions and answers in Ionizing Radiation, and find Ionizing Radiation experts.
Questions related to Ionizing Radiation
For radiologists, nuclear workers, and anyone who has to work with or is exposed to ionizing radiation.
Hey everyone!
I'm a PhD candidate in materials science, working on a novel ionizing radiation detector (mainly for dosimetry). Long story short, the technology has many possible development routes. As such, I am taking it to the end users and asking what are your biggest difficulties when it comes to equipment calibration. What do you wish the dosimetry equipment would be capable of doing?
Also, on a different note, what do you wish your personal dosimeter could do?
This is just preliminary research, would love to chat more with anyone interested!
Many thanks and truly appreciate your kind feedback!
Dear RG manager,
- As I wrote to you before, mon co-author is Kishor Mehta and NOT Kshitijkumar Mehta.
- Thanks much for taking in consideration my remarks.
- FYI, Mr Kishor Mehta passed away a few years ago.
Best regards,
Abdeljelil Bakri
Sterilizing Insects with Ionizing Radiation
Chapter
Full-text available
- December 2020
- Abdel Bakri
- Kshitijkumar Mehta SHOULD BE KISHOR MEHTA
- D. R. Lance
If yes how can I alter my input file for the corresponding application.
Hi,
As we know a scintillator is characterized by photon/MeV generated due to excitation of ionizing radiation. I wish to know which is the instrument/ set-up used for measurement of photon/MeV for a scintillator?
Hi everyone!
I am setting up an experiment regarding the analysis of several markers in cells exposed to ionizing radiation. I´m having some thoughts about choosing the most appropriate time, namely 24h after the last exposition to ionizing radiation, 72h or even longer etc.
What do you think is the most appropriate time point?
I've read many posts and articles touting the use of externally applied low dose radiation to the lungs to address the inflammation brought on by COVID.
Since, as pointed out in our paper on the possibility of a direct anti-viral impact from xenon-133, nuclear medicine lung ventilation has the unique ability to bring ionizing radiation to the entire respiratory system, shouldn't it be explored as a means to provide a more targeted low dose therapy than available from an external beam approach?
I'm trying to pass through characterization into normalization for a product which I found on literatture in an excel sheet.
The method I'm using is IMPACT 2002+.
I considered putting my impact categories as follows:
- Human health: human toxicity + respiratory effects + ionizing radiation + ozone layer depletion + photochemical oxidation
- Ecosystem quality: Aquatic ecotoxicity + terrestrial ecotoxicity + Terrestrial Acid/nutria + land occupation + aquatic acidification + aquatic eutrophication
- Climate change: global warming
- Resources : Nonrenewable resources + mineral resources
However, this calculation is incorrect according to the prior example, which was created entirely in SimaPro. I believe there are several factors that are missing.
Anyone could help me ?
the use of CT scan in addition to abdominal ultrasound to diagnose and to conform diagnosis of acute appendicitis has the hazard of exposure to ionizing radiation, so can we depend only on ultrasound with clinical correlation to make and conform the diagnosis ?
Hello every one
my question is about in vitro exposure of blood samples (blast cells) with ionization radiation to repair DNA damage.
The best
Hello all,
What is the best housekeeping gene to use on real-time PCR using cells cultured and subjected to different doses of ionizing radiation?
Thank you.
Elisa
I am ready to submit the thesis entitled "Study on the effect of MMP-2 gene silencing in the protection of human normal dermal fibroblasts and sensitization of MCF-7 human breast cancer cells from Ionizing Radiation"
Can anyone suggest foreign adjudicators for evaluation of Ph.D. thesis relevant to this area of research
All organs are not equally damaged by same amount of radiation dosage. But, on which basis equivalency is measured? (i..e 1 gray in this organ equals 10 sievert) Is it arbitrarily qualitative or quantitative as well? Then what is the quantity? ( concentration of reactive oxygen species, DNA mutation frequency, Radiative cellular apoptosis..., percent Coagulation of biomolecules). But all humans are not equally affected by same amount of radiation energy applied on same organ. Then, does the equivalency chart vary from person-to-person, species-to-species, or year to year ?(i.e. refining of values with increasing precision) I f so, thaen how the equivalency are standardized?
Hi. Anyone can give answer for my question?For your information I am not doing experimental works, as i am a mathematician. i am just developing a mathematical model of the effect or ionizing radiation by direct and indirect action. Thanks
I am searching about a software for analyzing of electronic and communication boards viewpoint of radiation tolerance. for example the output of this software is 40 krad. it means this boards can tolerate 40 krad in radiation environments.
I want to evaluate the ionizing radiation effects on miRNA expression level in mice.
Some paper used PBMCs and others used whole blood ( WBC ) for RNA extraction .
is there difference between these two source or which of them is better for this aim .
hi
I want to study the expression of XRCC2 gene (involve in HR) and XRCC4 gene (involve in NHEJ) after irradiation to ionizing radiation. These genes are involved in DNA double-strand break repair pathways of HR and NHEJ respectively.
what is the best time after irradiation to assess their expressions?
i studied some literature but I did not get a clear result
Is there an optimal time to express these genes at high levels?
Hello
there is a p-type of HpGe detectors, this kind is characterized by the litium dead layer wich existe in the outer side of the detector cristal and it is increased with the passage of time ( dead layer= 0,7 mm if the detector is new ).
On the other hand, the n-ype of these detectors is characterized by a very thin dead layer ( in order of 10E-4 mm ) in the outer side and gross daed layer in the detector cavity.
Flowing our monte simulation of the n-type HpGE using MCNP gives a clair contrast with the expiremental results. where :
MCNP effeciency /Experemental effeciency <1 .
The insertion of the a dead layer ( dead layer depth= 0,08 mm) in the simulation improve the results especially in the <100 keV energy range.
My quation is, do what i did is correct ? and this value of the dead layer is reasonable after 20 years of functioning ? especially that in the leterature, the study of the dead layer of the n-type detector is rare and it is limited for the dead layer existing in the inere part (the cavity).
Regards
If we irradiate MOSFETS by any ionizing radiation, change in interface trap charges is observed which varies surface potential. How can I relate these all with radiation dose --> then surface potential variation to get change in threshold voltage>?
I would like to know from your experience where the mistake is
Experimental steps include the use of sodium salt calf thumus and was diluted in TE buffer size 50 ml and at a concentration of 2 mg / ml l . After dissolving DNA for 24 hours at 4 ° C was exposed to eletctron beam 6 Mev from elekta preise linac (dose = 80 Gy and dose rate = 5 G / min, field size 20 * 20)
Then 50 mL DNA was divided into two glass petri dishes and a depth of each DNA solution in petri dish was ~ 1.6 cm and 1.5 cm water equivalent material was placed directly above the two plates without placing the cap petri dish. Gel eletrophorsis were then performed after a week of exposure and the sample in that period was reserved for the refrigerator at 4 ° C

Have a nice day everyone,
How does a Si/Ge photon detector discern energy from intensity, when both the energy of a photon and intensity of photons would proportionally contribute to the signal?
(The following is optional to read)
The working principles of energy-dispersive x-ray spectroscopy (EDXS) include the use of a semiconductor detector. The semiconductor is induced electron-hole pairs upon incident ionizing radiation. The number of induced electron pairs is proportional to the energy of the incident photon.
Ehv = N Eeh
where Ehv is the energy of an incident photon; Eeh is the electron-hole pair formation energy and N is the number of induced electron-hole pairs.
It is said that the detector use this proportionality to discern the energy of incident x-rays.
However, the number of induced electron-hole pairs is also proportional to the incident photon intensity/flux/number. Then we should also have
NhvEhv = Nt Eeh (I added this one. It was not written in the textbook.)
where Nhv is the incident photon number and Nt is the total electron-hole pair number induced: Nt = Nhv N
The question is: How does a semiconductor detector discern photon energy from photon intensity, if two of them both contribute to the number of electron-hole pair induced?
Have a nice day everyone,
The working principles of energy-dispersive x-ray spectroscopy (EDXS) include the use of a semiconductor detector. The semiconductor is induced electron-hole pairs upon incident ionizing radiation. The number of induced electron pairs is proportional to the energy of the incident photon.
Ehv = N Eeh
where Ehv is the energy of an incident photon; Eeh is the electron-hole pair formation energy and N is the number of induced electron-hole pairs.
It is said that the detector use this proportionality to discern the energy of incident x-rays.
However, the number of induced electron-hole pairs is also proportional to the incident photon intensity/flux/number. Then we should also have
NhvEhv = Nt Eeh (I added this one. It was not written in the textbook.)
where Nhv is the incident photon number and Nt is the total electron-hole pair number induced: Nt = Nhv N
The question is: How does a semiconductor detector discern photon energy from photon intensity, if two of them both contribute to the number of electron-hole pair induced?
Ruby (Al2O3 doped with Cr3+ ions), when exposed to ionizing radiation (for e.g. X-rays), emits luminescence. What is the mechanism that causes this 'Radio-luminescence? Does Cr3+ accept electrons or give up?
We are using gammaH2Ax as a biomarker for DNA damage in HeLa cells after exposim them to different doses of ionizing radiation.
Samples at 0 and 0.5 h from irradiation look normal, however, samples at 24 h from irradiation (both 0 and 4 Gy) display a strong signal from the whole nuclei for the filter corresponding to gammaH2Ax.
Anyone had similar experience or any idea about what could be wrong?
The protocol works for other cell lines- glioblastoma, fibroblasts.
And we had very high reproducibility (4 experiements in total).
For example, ionizing radiation induces multiple types of cell death such as apoptosis, necrosis, mitotic and autophagic. If, we can drive multiple into a single one, targetting the death can be realistic.
I mean how cell decides that which path they have to choose?whether it is "Karma" or "Destiny" ?
Hi, in the late '90s I used a software package from AIC Software Inc., called Photcoef, to calculate the ionizing dose / energy deposited and attenuation of x-rays and gamma rays through material stacks. This was very useful but the DOS software no longer functions and AIC no longer exists. Do you know any alternative that includes dose build-up due to generated electrons etc? I know I could use GEANT but this is rather too complex for my needs. Thanks Mark
Why organic materials were not used as bio-polymers, to protect against ionizing radiation. And why there are no studies and research on this subject
The most common way that conventional doctors look for the first signs of breast cancer in women is to identify lumps in the breast. They most often do this with mammogram x-rays. This offer physicians a basic road map for navigating the terrain of breast tissue, which they believe allows them to pinpoint any lumps, masses, or other warning signs of breast cancer that might point to a malignancy.
But mammograms can be a potential cause of cancer due to the ionizing radiation they send into breast tissue. They also aren’t accurate 100 percent of the time, despite what you may have been told. Lumps and masses in breast tissue can be either benign (harmless) or malignant (cancerous), and mammograms don’t differentiate between the two. This often leads to false diagnoses and unnecessary treatments with chemotherapy and radiation
is there any information about Is there any information about the diagnosis or early signs of this disease? share with me ...
ICRP-118-2011) Published new version decreased dose limit for occupational workers from 150 mSv to 20 mSv but i did not find any publication concerning any change in eye lens dose limit for public.
I am part of the scientific team of a mission of young researchers to send a biological mini-lab to the Moon thanks to the company Team Indus. Our experiment requires real-time measurement of ionizing radiation on the Moon. Thanks to data from the NASA mission Crater we can see that the range of radiation intensities are in the range of 0.001 to 0.01 cGy / day and during solar events can reach values of 100 cGy / day.
Just wondering if anybody has ever done this. I would suppose the oligos could suffer, since they´ll be exposed to ionizing radiation for a brief period... but i´m not quite sure if enough to destroy them.
I want to determine the absorbed dose of x-ray and Gamma ray of human body when it's ionized radiations are used in medical application
Why Ionizing Radiation is known as a double edged sword?
What is meant by RBE (Relative Biological Effectiveness)? Does RBE varies with increasing LET?
Why are some isotopes radioactive and others not? Can you predict which ones will be radioactive?
What is meant by prodromal syndrome? At what total-body absorbed dose range this syndrome resulted?
Do you have any information about Dr. Luckey's work and where can you get more info on "Hormesis".
Why and How does Fractionation introduces a "waste in dose", which is more pronounced for beams with a wide shoulder than for beams with a narrow shoulder in the survival curve??
How oxygen plays role in lethality of ionizing radiation?
Background radiation is the ionizing radiation present in the environment. Background radiationoriginates from a variety of sources, both natural and artificial.
I am looking for a measure of the time scale between direct irradiation, and bystander effects being observed in vitro. I have a mathematical model that predicts this, and would like some validation.
I am trying to have human fibroblast irradiated by Ionizing radiation(Cobalt 60).
I encounter some problem during the experiment.
I tried to use 10/30/100 Gy of IR on fibroblast cells, and after 24 and 48 hr incubation, I couldn't see any floating cells(dead cells). All of cells were attached, and I assumed all of them were live cells. This seems very weird, according to most of papers which use dose of 5-20 Gy for measuring apoptosis of cells.
I am wondering in your experience whether after radiation and incubation, the cells had some portion of floating cells, or there were no any floating cells and apoptosis assay could recognize those apoptotic cells.
I hope to have some suggestion from your response.
Thank you very much.
I have access to a x-ray irradiator but not a gamma ray irradiator.
Due to the interaction of such radiation with matter, a small charge will be formed on the material surface. This charge must be safely leak out; therefore such shielding material must have good electrical properties.
Use of dicentric counting Chromosomal aberration test for biodosimety for ionizing radiation is very common technique. How much reliable method is this ? i m worried about this because of limited number of dicentrics formations in the exposed person.
Hi all, this is Wen. I am working on an ion beam irradiation program. Now I have calculated the dpa (displacement per atom) of the beam on the target, but I don't know how to evaluate the total dose needed to fail the target. This is essential to my program but I have never worked on such problems before. Can anyone teach me?
Thank you so much.
D. robiginosus was isolated from a sterilization dose audit. Have you performed any D10 assessments following exposure to ionizing (gamma) radiation?
Numerous papers have reported increased invasion of cancer cells after treatment with high doses of ionizing radiation. I have seen this in my work with lung cancer cells as well. Is there a common biological explanation for this observation or do different cell lines activate different pathways that increase invasion of the cells?
Dear All,
I was wondering what analytical method I should utilize in order to detect any chemical alteration in an organic sample that is irradiated by X-ray radiation?
Note: The color change was observed as a result of irradiation.
Best,
Sevan
There are many dosimeter available in the market especially online. How do one ascertain if a particular dosimeter one should use for measuring the quantity of ionizing radiation of a device e.g mobile phones is effective and accurate particularly when it is to be purchased from online store and there is no sample?
In the literature it is said that the grainless nature of radiochromic films is responsible for their high resolution. What exactly does this mean?
I am planning to perform double strand break (DSB) assay to test how cells response to DSB (patients vs controls) (general design: induce DSB and measure the level of γ-H2AX foci). I could see that there are 2 main options to induce DSB: ionizing radiation or agents (e.g. ETOP). Can I choose either option or should I need to consider some factors to choose the appropriate option? If it's the latter, what factors are they?
(I'm plannning to test on primary human peripheral mononuclear cells (PBMC) extracted from blood as well as EBV-transformed PBMC.)
Thanks.
One of the ways through which Crystalline materials turning amorphous is under swift ion irradiation. Crystalline materials can also be amorphized via ball milling, owing to impact-induced crystal attrition. Now, considering the final state of the material being same (amorphous), can we draw any similarities between the two processes in terms of its path or mechanism to reach amorphous state ?
We want to determine/understand DNA damage/mutation caused by different doses of gamma irradiation on different organisms. However, although I have performed DNA sequencing using Genetic Analyzer 3500, but I don't have any experience on determining DNA damage/mutation caused by ionizing radiation. Those who have experience on this field, please provide your insightful guidelines on this issue.
Thank you very much.
I tried searching it in google indeed, but just found some old and new articles on modeling of radiation environment that were of no use to my problem. What I'm exactly looking for is a set of information like what we have for gravitational field (Spherical harmonic coefficients) that describes the magnetic field strength and charge densities in proportion to solar activity.
Let's put it this way: I want a model to use it to calculate the amount of radiation dosage absorbed by spacecraft in a trajectory around Jupiter (or Earth) for a certain amount of time.
Dear Colleagues,
in order to shield a dose rate (NORM in drums) from about 250 micro Sievert per hour, down to about 5 micro Sievert per hour, I have calculated a lead sheet shielding of about 17 mm thickness. Is there anybody to confirm this result, respectively giving a more detailed input on this topic such as literature or examples, standards etc.
Your kind support is highly appreciated
Ruediger
Exposure of the heart to ionizing radiation during radiotherapy for breast cancer may increases the subsequent rate of ischemic heart disease.
As the biological effect of radiation is measured in Sievert, I would
like to know if and how one can convert W/meter square or dBM of a
non-ionizing radiation into the unit Sievert?
Under ICD-10, a new entity has been recommended [Z58.4] for disease due to exposure to radiation, or EMF syndrome. Though safer than ionizing radiation, too much of non-ionizing radiation can be unsafe, but requires lot of efforts to demystify the reality.
Consider a solid sphere of some material and a spherical shell of the same material with both having the same thickness in the sense that a straight-line path from outside to the center travels through the same thickness of material. These are intended to be used as radiation shields in a given external electron environment. The interest here is the ionizing radiation dose at the center of each. Because electrons do not follow straight-line paths when going through a shield, I am not surprised that the solid sphere and spherical shell will not produce identical doses at the center, but how much different should they be? And why? Is there some simple analytical argument (not Monte Carlo) that can roughly account for this difference?
Dear engineer Why win-q disconnected to quantulus 1220?.what can i do to solve this problem.I turn on and off system and counter but win-q display disconnected massage in application.I reinstalled app. But win-q is disconnect .at first its error was conveyor clearing but after turn off & on it shows disconnected. we check the plates and remove trays and check them.they dont have any problem. please answer my question. I need to answer .best regard((when counter time was over the elevator took vial at tray and after that we hearing the pneumatic pomp tone(Eu-152,STD capsule) more and more.after that we turn on & off several times.but after that application showed disconnected))
best regard.
I have been using the unit: umol m-2 s-1 to talk about photosynthetically active radiation, but is it wrong in the International System of Units?
In gamma irradiation of polymer experiment, which surface is more influenced, the entry or the exit surface and why?
and when the film thickness is in micro range, is that make difference? or is there a difference between the entry and exit for small thickness samples?
what about gamma attenuation in polymers is it effective to use polymers as a shielding material since it is rich of hydrogen.
please give some details in your answer??
During XPS / ESCA Analysis
Dose the charge effect of irradiating ions play a part in the radiation damage build-up in materials? e.g., the Xe+ and Xe26+ ions induced damages in a specific kind of material are due to the same or different mechanism?
Thanks in advance!
OR, does the use of these radionuclide tracers, themselves, add a significant risk of causing cancer in patients?
The dose of ionizing-radiation from the tracer used in one PET scan, for example, typically exposes the patient to about 25% of the maximum allowable annual radiation exposure permitted for nuclear workers (which is a VERY high limit = to over 200 standard/modern medical chest xrays, meaning a patient is getting exposed to the equivalent of about 50x chest xrays ALL AT ONCE for each PET test).
Is it possible that XRD peak intensity decresing with increasing ion irradiation ?
Although, senescence and mitotic catastrophe are 2 independent processes, I have observed cells with enlarged appearance, highly polyunucleated and with micro-nuceli that stain positive for beta-galactosidase activity.
I'm using the Quantulus Liquid Scintillation Spectrometer with the Perkin Elmer Filter Count scintillation cocktail in a plastic vial to measure the activity of Am243 and Am241 (separately) in two different conditions: radionuclide dissolved in an homogeneous solution and radionuclide deposited on a borosilicate glass filter immersed into the scintillation cocktail into the vial.
When I measure the Am243's CPM (counts per minute) I always obtain a 180-200% efficiency (CPM/activity[Bq/min]). When I measure the Am241's CPM, instead, I have an averaged efficiency of 86% in the homogeneous solution and an averaged efficiency of 120% with the radionuclide deposited on a borosilicate glass filter.
With respect to the Am243 I know that the Am243 (100 % alpha emitter - Qalfa=5.438 MeV - Half life= 7370 years) decays in Np239 (100% beta emitter - Qbeta=722 keV - Half life=2.3days) so I thought that the 200% efficiency was due to the secular equilibrium of the Np239 even if the Quantulus should discriminate the beta emissions and the alpha emissions. The problem is that the instrument doesn't show the presence of Np239 in the scintillation spectrum. Is this consideration acceptable in your opinion?
Regarding the Am241(alpha emitter - Qalfa=5.958 MeV - Half life= 432 years), it decays (alpha) in Np237 (100 % alpha emitter - Qalfa=5.438 MeV - Half life= 2.144*10^6 years) that is in transient equilibrium with the parent element. So I think that the presence of Np237 in the scintillation spectrum is negligible. In this case I can't explain the averaged efficiency of 86% in the homogeneous solution and the averaged efficiency of 120% with the radionuclide deposited on a borosilicate glass filter. Could anyone help me with this?
It is easy to produce linearized ends with sticky ends using restriction enzymes and these sticky ends are readily ligated by DNA ligase enzyme alone without the need for DNA end-processing.
How do I make such linearized DNA behave like the DNA breaks created by ionizing radiation where DNA breaks need end-processing before DNA ligation can proceed.
In simple words, how do I create a linearized DNA with sticky ends resembling radio damaged 'non-ligatable' ends.
Not interested in 'dephosphorylation'.
Can someone direct me to one such method, if it exists, please.
There are various methods available in the literature (Initial Rise, Peak Shape, Glow curve deconvolution etc.) which are used to analyse a thermoluminescence glow curve that recorded at a linear heating rate. But if the heating rate is not linear is there any method to accurately estimate the trapping parameters from the glow curve?
The International Commission on Radiation Protection (ICRP) proposed a set of operational quantities defined to allow for calibration of ionizing radiation protection instruments for measurements to show compliance with the system of protection quantities. These measurable quantities are the ambient dose equivalent, the directional dose equivalent, and the personal dose equivalent.
An earlier question "What is the difference between Sievert and Gray? A practical question concerning the SI units for ionizing radiation?" addressed the confusion of Sievert and Gray and its use in radiation protection programs. This question is a continuation and addresses the practical aspects of calibrating and interpreting instruments used for radiation protection.
The ICRP asserts it has proposed measurable quantities, but have defined them by calculation. The calculation is ideal and impractical for measurement as a parallel expanded beam of a single energy is not possible to produce. The point of dose is at a depth in a sphere or slab, a location not accessible to an instrument. Actual calibration must be performed free-in-air with a non-uniform beam and with physical constraints that may not be negligible. Calibration is to an instrument that is energy dependent and does not have the backscatter characteristics of a sphere, slab, or human body.
In theory an alpha particle has 2 electron holes giving the particle its ionic charge. With the alpha particles' velocity, could a series of dropleton like phenomena be formed in its wake until enough energy is transferred away from its velocity for electrons to achieve a stable orbit around the emitted nuclei? I'm currently looking at radiation effects on lung tissue in mice and would love to be able to apply these observations with some confidence in my write ups.
Oxygen metabolism is key to eukaryotic life and important for signaling as well as metabolism. Yet, ROS are linked to cancer and aging as well as inflammation. There is also a possible link between stem cells and levels of ROS. With new in vivo imaging, and other methods ROS levels may be more evident at the individual cell level and in response to environmental stresses.
I want to treat the soybean seeds with an electron beam to enhance the overall food quality.
Is there is any type of effect in reducing or increasing the formed nuclear tracks?
This question is about radon or radium measurements by using SSNTDS e.g.CR-39.
I mean the effect through the exposure time.
I am soon going to be learning the separation process for micas and zircons. To get Ar/Ar ages for the micas, they need to be sent for irradiation. Could anyone give me an idea of how long the irradiation process should take and what factors are involved in the process? Alternatively, could anyone point me to some articles/papers that describe the process?
N1mmonia gas has Lambda Max between 212-215 nm. Is it possible to decompose Ammonia [2NH3 + hv ---> N2 + 3H3] using Ultraviolet radiation? If it is possible, how much (power) watt will be required to decompose one liter of ammonia in one minute? How we can increase the rate of decomposition of ammonia?
and is there a free software that calculate the tristimulus valus and color change? also please provide a reference?
what is the deference in measurements if we measure radon and radium by using CR-39 and LR-115 detectors?
Instruments and dosimeters are calibrated in Sv or Gy. What is the interpretation at your institution (regulatory authority) of the measurement? If calibration to Gy do you convert to Sv for reporting purposes? I am not asking for the definition of Sv and Gy as in ICRU 57. My question regards practical definitions and usage. Please see the recent question by Anuj Soni, what will be the skin dose in the case of a pure gamma field? and discussion. The definitions I use are a strict interpretation of ICRU 57 Sv is effective dose based on weighting factors and Gy is organ dose based on measurement (modeled from measurement).
1. What will be the skin dose in case of pure gamma field? Can we multiply the whole body dose (Hp10) by weighting factor (0.01) and add to the whole body dose?
2. For example, If the whole body dose to worker is 2 mSv (no beta dose), what will be the skin dose?
3. In case of NPP where beta is also there, can we add the dose to skin due to gamma to the dose to skin due to beta ? Also what is the procedure to find the skin dose due to beta alone ?
4. What is the percentage of skin dose due to photons? How it varies in case of isotropic source and collimated beam source. Also how it varies with field size and source to surface distance (SSD) ?
5. How can we experimentally find the percentage of skin dose in case of pure gamma field using ionization chamber/TLD?
6. Is there some IAEA document dealing with reporting of doses for occupational workers?
Why is the total mean annual effective dose for infants greater than children as well as adults?
I'm interested in the spectral response curve.
For example, Shewanella oneidnsis was shown to be more sensitive to gamma radiation than most bacteria. Is this a general pattern for metal reducers?
I'm trying to find out or estimate the total number of radioiodine treatments in the USA, EU or world wide. Have tried to look in different IRCP and UNSCEAR reports, but can't locate an answer. Does anybody know of other official sites or publications that can bring me closer to an estimate?
I use gamma radiation to study a phenomenon, but would like to extrapolate my finding to natural setting based on the similarities between gamma- and UV- induced damages.