Radioactivity - Science topic

Very interesting study . You write :…male Balb/c mice exposed to varying radon concentrations showed significantly improved survival rates after gamma irradiation compared to mice that weren’t exposed to radon.

meanwhile as I know the predominantly radiation mass of radon is alpha radiation. Charles Darvwin taught us : survive not who is cleverer but who adapts…

I can't imagine this to be practical. We are talking about No-259 with half-life of 58 minutes, which alpha-decays to Fm-255 with half-life of 20 hours, which alpha-decays to Cf-251 with half-life of nearly 900 years, which can be considered "stable" for the intended application.

But why bother to have two alpha decays per atom (producing radiation and its associated problems), when you could start-off with Californium (Cf) in the first place? To try to answer your question: I am guessing it might be possible, but is it worth the effort?

Hi Adam Szewczyk , your question does not include probably one of the most important information; what radionuclides are you dealing with? Basically, the type of radiation emitted defines what detector you could use. For alpha/beta emitters, whole body scan is extremely challenging (close to impossible) even if there are characteristic x-rays emitted.

The next thing to consider is the biokinetics of the radionuclides; for example, if it is a bone-seeker (Sr-90) the localization may be straightforward. But, if you have something soluble then it can be very difficult to localize. Unless, of course you are looking at the bladder and maybe the kidneys and liver.

Another thing to consider; depending on the activity present, the measurement time required to get a good signal (with high confidence) can be too long for an individual to stand still. Therefore, the detection efficiency should also be considered.

These are some things I believe you should consider when you researching what detector may fit your needs.

Good luck,

dimitris

Storing radioactive cell samples in liquid nitrogen for extended periods can sometimes lead to changes in cell surface marker expression, which might explain the shift in the CD45 positive population you observed. Here are some possible reasons for this phenomenon and suggestions to mitigate it:

### Potential Issues

#### 1. **Cryopreservation Effects**

- **Cell Membrane Integrity**: The extreme cold of liquid nitrogen can sometimes cause damage to cell membranes, affecting the binding of antibodies to cell surface markers.

- **Ice Crystal Formation**: Improper freezing rates can lead to the formation of ice crystals, which can physically damage cells and alter the expression of surface markers.

#### 2. **Freezing and Thawing Process**

- **Thawing Method**: Rapid or uneven thawing can cause cell stress and affect the integrity of surface markers. It's crucial to follow a consistent and controlled thawing protocol.

- **Cryoprotectant Use**: Ensure the appropriate concentration of cryoprotectants like DMSO is used. Incorrect concentrations can either be insufficient to prevent ice formation or toxic to cells.

#### 3. **Radioactivity Effects**

- **Radiation Damage**: Prolonged exposure to radiation, even at low levels, can cause cellular stress and alter cell surface proteins. Ensure that the level of radioactivity is within safe limits for the cells.

### Best Practices for Cryopreservation

1. **Optimized Cryoprotectant Protocol**

- Use 10% DMSO in combination with a suitable medium (e.g., FBS or a cryopreservation medium) to protect cells during freezing.

- Aliquot cells into cryovials at a consistent cell concentration (e.g., 1-5 million cells per mL).

2. **Controlled Freezing Rate**

- Use a controlled-rate freezer to gradually cool the samples to -80°C before transferring them to liquid nitrogen. A typical rate is -1°C per minute.

3. **Thawing Protocol**

- Thaw the cells rapidly by placing the cryovial in a 37°C water bath. Once thawed, immediately dilute the cells in pre-warmed medium to reduce the concentration of DMSO.

- Gently mix and then centrifuge to remove the cryoprotectant.

4. **Handling Radioactive Samples**

- Store and handle radioactive samples following all safety protocols to minimize any potential radiation damage to the cells.

- If possible, reduce the storage time of radioactive samples in liquid nitrogen to the minimum required.

### Recommendations for Flow Cytometry Analysis

- **Staining Procedure**: Ensure that the staining protocol is optimized for cryopreserved cells. Sometimes, slight modifications are needed compared to fresh cells.

- **Compensation and Controls**: Use proper compensation controls and unstained controls to accurately set gates and distinguish between positive and negative populations.

### Literature and Protocols

1. **Cryopreservation of Cells**:

- Mazur, P. (1963). "Cryobiology: the freezing of biological systems." Science, 138(3544), 1271-1279.

- Stacey, G. N., & Hartung, S. (2006). "Cryopreservation and banking of human ES cells." Nature Protocols, 1(1), 212-218.

2. **Flow Cytometry on Frozen Samples**:

- Perfetto, S. P., Ambrozak, D., Nguyen, R., & Roederer, M. (2010). "Quality assurance for polychromatic flow cytometry." Nature Protocols, 5(2), 445-456.

By following these best practices and protocols, you should be able to improve the viability and performance of your radioactive cell samples during cryopreservation and subsequent flow cytometry analysis.

Dear Sir,

Thank you very much for your kind message and congratulations on your book. Unfortunately, I am not able to purchase it, but it is really very interesting.

Let's keep in touch.

Regards,

Naima

Thank you Shekh Mohammad Mostafa for your answer, but it seems like a CHATGPT answer, no specific selectivity.

Dear Amina el Rhalbi, you forgot to add the link or the DOI of the work you follow. Generally speaking, the amount of resin depends on the level of radioactivity of the contaminated product. The confinement seldom use neat resins, usually special additives are added. My Regards

vous avez oublié d'ajouter le lien ou le DOI de l'article que vous suivez. D'une manière générale, la quantité de résine dépend du niveau de radioactivité du produit contaminé. Le confinement utilise rarement des résines pures, généralement des additifs spéciaux sont ajoutés. Mes salutations

Hi,

you only need to collect information about Korea?

As I understand you mean studies on natural radioactivity. Due to the increase concentration of natural radionuclides in industrial by-products, such as fly ash and silica fume, concrete produced by these SCMs can have high 226Ra, 232Th and 40K activities which emitting various energy levels of photons (gamma rays). Indeed, ordinary Portland cement has a significant natural radioactivity potential, as well. Natural aggregate sources contain negligible amounts of natural radionuclides. Accordingly, you can focus on the papers about the sources of natural radionuclides (226Ra, 232Th and 40K) in concrete ingredients. Please see the paper

Dear Philippos Afxentiou ,

If gravity is well defined as is in reality... Gravity is connected to electromagnetic phenomena of course can get the connection between gravity and radioactive phenomena/effects.

I have the resolution...

My concept has the next prediction: Take a relatively rapidly beta-decaying radioactive element in a very thin and strong insulating box, on the outside we will experience an effect that increases the moment of inertia.

t can be proven exactly experimentally

Regards,

Hi there,

If your enzyme of interest is produced then there might be an issue with its folding/stability (if not properly folded/matured the protein will exhibit no activity), cell extraction (possibly provoking the loss of enzyme activity) and/or with the assay itself (compatibility with the source of enzyme you use).

Dear Tristan,

to which sourc(es) of Cs-137 does your question refer to and in which part(s) of the Pacific?

In respect to known recent or ongoing instances of Cs-release such as at Fukushima or during 20th century nuclear tests in the Pacific, I do not deem the potential effects you inquire about likely. I think such impacts to be detectable would require more substantial amounts to be released, e.g. point sources of big quantities at very localized areas. The short half-life of Cs-137 (~ 30 a) would also constitute an important aspect of consideration there.

Hope this helps a bit...

Best,

Julius

I assume that the question refers to the risks of radiation in genetic material.

If so: https://www.ncbi.nlm.nih.gov/books/NBK218706/#:~:text=Ionizing%20radiation%20damages%20the%20genetic,transmitted%20from%20generation%20to%20generation.

Hello,

Filipin is my first thought but You may have a look to this article for more probes:

Hello, in many publications the Histone H2A.XS139ph antibody is used against a peptide including phospho-serine 139 of histone H2AX.

Dmitry Milovzorov: Yes sir , I agree with your answer but I emphasized that there are undiscovered methods

You should add to the rule "too many n" and "too many p" the words "compared to the stable isotopes of the same element", i.e. 69Ga and 71Ga.

But this remains a gross rule. Some nuclei with "too many protons" undergo electron capture , not beta+ decay.

The exact rule allowing beta+ is that the mass of the parent 68Ga is higher than the sum of the masses of the progeny 68Zn + 1 positron.

Neutrons and protons, like electrons in the atoms and molecules, behave randomly, although following probalistic rules, as it is the case for all processes at atomic and nuclear scale, that are described by the probalistic laws of quantum physics.

Thus the radioactive transformation occurs randomly. Even if they have the same composition and energy, two nuclei of the same radioactive nuclide are never in the same internal configuration.

you can use biomarker techniques which is the same as scintigraphy and see the cholesterol pathway

No. See: https://en.wikipedia.org/wiki/Nuclear_binding_energy

A quick glance at 238 nucleonc each having binding energy of about 8 MeV

With C = activity concentration in Bq/l, volume V[l]= Mw mass of water in kg

and MCs= mass of Cs137, Avo= Avogadro number 6.02*10^23 atoms/mol

Atm= atomic mass 137 g/mol , T1/2 in sec

activity = C * Mw[kg] = ln2 *MCs[mg] * Avo / (T1/2 * 10^3 * Atm)

ppm = MCs[mg]/Mw[kg] = C[Bq/l] * T1/2 * 10^3 * Atm / (ln2 * Avo)

A very low concentration indeed, even for a high activity.

In general marble, a metamorphic rock has very low levels of radioactivity.

To measure radioactivity in the human body it is necessary to have a good radiation shielding around the detector and the subject. The shielding is in this case built of massive steel stabs of naval armour- plate forming an iron room The iron room is ventilated with filtered air.

as a result the detector is sensitive to gamma-radiation with energies above 50 Kev and supplies information about the energy of the gamma photons, which makes it possible to identify the gamma emitting isotope measured by the spectroscopy. A certain hour measurement offers the possibility of detecting of a 100 % gamma emitting isotope distributed in the nail at the gamma energy is above 50 Kev.

The purpose is to look incorporation and metabolism of an exogenous lipid. So yes, isotope labeling can be used. I guess that in this case, you have to mark the C atoms.

Anyway, now there are fluorescent lipids commercially.

Hello Andreé Brink ,

All the methodolgies for dealiing with the intake and discharge of radionuclides in the human body seem to be derived from ICRP Publication 2 (1959), URL: https://journals.sagepub.com/doi/pdf/10.1177/ANIA_OS_2_1 . But this document is only for continuous occupational exposure: 40 hours/week, 50 weeks/year for 50 years, and the compartmental models of the organ systems are very crude.

But to your contention about being the last person out, let me say this. You need to distinguish between a Three Mile Island event versus a Chernobyl event. In a Chernobyl-style event, where the core melts and the graphite moderator catches fire and the resulting smoke leaves through the wreakage of the reactor building caused by the explosion, the least of your worries will be exposure to I-131 as the smoke will be filled with radioactive metal oxide particles, which, when inhaled, will be lethal. In comparison, the Three Mile Island event, even though it damaged the core, did not breach the reactor vessel nor the containment building; in the Chernobyl event, not only was the lid to the reactor vessel blown away, but there was no containment structure just a flimsy reactor building, which was easily breached by the expolsion.

Regards,

Thomas Cuff

You may also want to check Fispact-II. This code does not require geometry simulation so it can be on the conservative side. It is similar to SCALE's Origen but FISPACT-II provides the ability to include protons. Additionally, the stand-alone ORIGEN will help you only if you know the radionuclide concentration right after the irradiation has ended. As far as I know SCALE is about neutrons/photons. I hope this helps.

Tracers were used to quantify rechages of SAS (Saharian System Acquifer) al almost fossil acquifer.

Informations about SAS are provided in our two books:

(6) Sécurité Hydrique de la Tunisie, Gérer l'eau en conditions de pénurie | Request PDF (researchgate.net)

We are allowed to communicate copies of the book in french in the scientific sphere, just request on my RG page. Unfortunately, we are not allowed to do so with the English book

More resources on water resources in the arid zone can be found on the following projects referenes:

I'm interested. We can do a review in NORMs; (Whatever it's type)

Everyone will do a task in it.

Those who are steady can contact with me through the email:

📷

thanks

This is one that I can think of. Hopefully it will help.

Plutonium isotope such as Pu-293 is a fissile, so can be harvested, then recycle to be used as fuel. Some reactors have fuel assemblies where, there is space on the upper part of the fuel rod, which allows isotopes produced such as Pu-2393 to occupy the region, thus act as the new fuel. Of course there are downsides.

The answer of Dr wael badawy is complete. Nothing can be added to his answer. However, in case of using gamma ray spectroscopy, one will need a large quantity of the samples prepared. This will depend on the level of radioactivity. The lower the radioactivity, the larger the quantity samples needed.

Dear sir,

You can look to this paper.

I guess you talking about something like Co-60 1.17+1.33 = 2.5 MeV.

That comes to probability of detecting both gammas. E.g if you bring the detector closer the fraction of the events in combined line will relatively grow . Note that there might be or is (at least in case of Co-60) angular correlation/anti-correlation of emitted gammas.

So in simple case if you detect first gamma (as photopeak not Compton partial event) with probability a1, the second one with a2 the fraction of of combined line over total photopeak events will be simply a1*a2 /(a1+a2+ a1*a2). Note that some 'pot' or 'well' type gamma detectors may have a1,a2 approaching one for some cases.

Using flow cytometry in the study of cells treated with radioactive isotope, it is possible that some of the radioactivity will remain on the tubes and nozzle. Therefore, you need to know the methods of dosimetric measurements and methods of cleaning radioactive substances from the surface. You must obtain a special work permit from the owners of the device. The same applies to fluorescence microscopy.

If you do not do this, then you need to wait for the level of radioactivity to subside. But how long it will take depends on the half-life and the amount of radioactive material.

I wish you success!

For the detection of ionizing radiation, germanium detectors are most often used, they are widely used in gamma-ray spectroscopy due to their high resolution and high detection efficiency compared to their analogues. An increase in the radioactivity of natural radioactive isotopes in hospital wastewater is observed due to the use of radioisotopes in the diagnosis of diseases in hospital patients.

It depends on what sewage sludge contains before treatment and after treatment. For example, if the activity level was high, then depending on the sewage sludge treatment method.

https://www-pub.iaea.org/MTCD/publications/PDF/te_1598_web.pdf

Dear Moamen G. El-Samrah ,

the two P isotopes you mentioned above are ³²P and ³³P ; you are right, they are beta emitters. Their half-lifes are 14,3d (³²P) and 25,3d (³³P). All other radioactive P istopes have much smaller life-times. In consequence all 'natural' radioactive P isotopes will have been disappeared since their birth in an exploding star. The natural abundance of the stable ³¹P is 100%.

So there is no necessity for Nibras Seed to set up a 'beta spectrometer'.

I agree with you to use a HPGe detector for the acquisition of a gamma spectra, to have best energy resolution for the elemental identification of the gamma emitters in the sample.

Khaled Ali Thank you for this informative source

Bergonie-Tribondeau's law based on experimental observations in rat testes applies at cellular levels (albeit with various exceptions such as lymphocytes, some gonadal cells, AT cells, and SV40-transformed cells), but less generally at tissue or organism levels. Younger people are not necessarily radiosensitive than older people where dependence of radiosensitivity on age (e.g., age at exposure, attained age) greatly differs by endpoints (health outcomes). For instance, children are more radiosensitive than adults for about 25% of cancers (e.g, leukemia, thyroid, skin, breast and brain cancers), as detailed in

Hi Niels Wolff ,

Mathematically, if your independent parameters are H, r, C=1.5e-15, E, n, B, M=exp(-μd), and their uncertainties are ΔH, Δr, ΔC, ΔE, Δn, ΔB, ΔM, then

A=H r^2/(C E n B M)

(ΔA/A)^2=(ΔH/H)^2+(2*Δr/r)^2+(ΔC/C)^2+(ΔE/E)^2+(Δn/n)^2+(ΔB/B)^2+((ΔM/M)^2).

You need all uncertainties of the parameters used for determining A.

Hello.

The answer is not so simple as it may seems.

Firstly let's make an experimental setup clear.

- Lets suppose we are talking about a laboratory experiment (not some kind of outdoor measurement)

- radioactive sources are point-like and solid-state. (I.e. with no self absorption, no diffusing or flowing gasses or liquids, with no affinity to aerosols)

- it is an isotropic radioactive source without beam collimation

- radioactive sources are relatively close to each other (lets say 10 cm as you suggested)

- there is a standard atmospheric air between the radioactive sources, free of 222Rn and filtered for aerosols

- lab is perfectly shielded from surrounding environment and cosmic rays

- construction materials of experimental setup are free of radioactive isotopes

Then the measured activity of low radiation samples may strongly depend on where exactly is "somewhere in between".

First of all, isotropic flux of particles of photons (in vacuum) decreases as square of distance from source.

Flux of particles at particular point in space filled by some medium (air) depends on ability of particles to penetrate it. For example alpha particles are a highly ionizing form of particle radiation and can be completely stopped even by a few centimeters of air (depending of alphaparticle energy).

Therefore, it is extremely important to know the details about the experiment to design the setup properly.

Bye, JS

سؤال جيد ومهم

Hi Sebastián Alejandro Sarasti,

The most significant difference is the width of the photoelectric peak at 662 keV. This width occurs after gamma-ray energy is transferred to the scintillator crystal. Your simulation probably may not include this part.

The number of scintillation photons generated, when 662 keV is totally absorbed by the NaI:Tl crystal, is statistically distributed. It is also a stochastic process whether each scintillation photon is successfully detected by a photodetector (photomultiplier tube or semiconductor device) or lost.

There are two ways to improve the distribution. One simple way is to assume the energy resolution of the detector (crystal + photodetector) and perform a convolution with your results. You can fine the typical energy resolutions in literature: typically ca. 7% [*].

Another detailed method is to add, if necessary, simulation to track the behavior of the scintillation photons.

The other differences seem to be related to Compton scattering; since the NaI:Tl crystal is sealed in a package, some of the energy may be lost by Compton scattering in the package before it enters the crystal. Then, the gamma-ray energy is not 662 keV but less than 475 keV for the detector. Similarly, Compton scattering from surrounding desks, walls, and other objects may enter the crystal and increase the proportion of that component of the experimental data.

Hi,

when you use radiolabeled solution you can use the Liquid Scintillation counting to detect the signal, and this method is very good and with high-quality skills, such as very good sensibility, in some case very easy sample treatment...

In my opinion, you should consider:

- H-3 or C-14 or other radionuclides (such as Iodine, 125, 131 or 129, Luthetium 177): what is the chemical behavior that you needed? H, C, or other, what is the best solution for your molecula?

- Kind of emission from radionuclides: beta? Alpha? EC or x/Gamma? You speak about H-3 and C-14, beta emitters, with respectively low energy and medium-high energy. LSC is the best to measure beta emitters in liquid samples.

- How much Bq do you need? Before starting with the measure with LSC, you should know the MDA that you can have with the blank sample. When you have this information, you can know how much Bq of radiolabeled solution use, or how much cost the experiment.

Be careful, there are a lot of LSC's instruments...but they are not cheap.

Maybe here you could find some info:

te_1528_web.pdf (iaea.org)

or

46135125.pdf (iaea.org)

Best Regards

Mattia

Subcellular fractionation can be done using a series of specific extraction buffers (e.g., for nuclear, cytoplasmic, membrane): typically within 2 hours when commercially available kits are used. “Purity” of yielded fractions can be checked, e.g., by western blotting for compartment specific marker proteins.

Darkhan Sairanbayev

use like this

sdef erg=d1 ....

#si1 sp1

....

add spectrum energy and spectrum probability

if have more problem contact me

In addition you could use the thin sections/polished section of minerals/rocks using EPMA or any other related facility. These are most suited and extensively used for identification of radioactive minerals and whether comprise of primary or secondary uranium and/or thorium enriched minerals.

Hello Dear... to be safe you must be using dosimeter for beta detection like Liquid Scintillation Detectors and you should be known there is no zero risk with RADIATION

Dose rate to the skin at 10 cm: 625 mrad/hour/mCi (for an unshielded point source)

Dose rate to basal cells from skin contamination of 1 mCi/cm2: 1460 mrad/hr

Shielding: None needed, when used in millicurie quantities under normal laboratory conditions

Annual Limit on Intake (ALI): 10 millicuries via ingestion for most compounds of sulfur. The intake of one ALI will produce a dose of 5 rem.

Detection

Wipe surveys using liquid scintillation counting is the preferred method for detecting S-35. Most G-M detectors are not likely to detect the presence of S-35 in amounts less than about 100,000 dpm (0.05 µCi).

Precautions

35S-labeled methionine/cysteine compounds can volatilize. Stock solutions and thawed materials should be opened within a fume hood. Activated charcoal can be used to trap contamination within equipment such as incubators. Contact EHS for further information.

Low-level S-35 contamination cannot be easily detected with a G-M meter, and special precautions are needed to keep the work environment clean. The regular use of wipe testing, using a liquid scintillation counter, is the only way to insure that the work space does not contain low-level removable contamination.

Yes

Q and A are parameters used for standardization and safety of drugs in pharmacology. Quality assurance is an integral part of traditional medicine, which certifies that it delivers the required quantity of quality drug. The standardization parameters are authentication, foreign matters, organoleptic evaluation, microscopy, volatile matters, extractive values, ash values, radioactive contaminants, microorganisms, pesticide residue, refractive index, chromatographic profiles and marker components.

Dear Maria Mihalache ,

you can do this. I assume that there is no Uranium in the sample iself.

So the sample will not still emit x-rays or gammas due to Uranium radiation.

Nevertheless you should perform two measurements:

a) perform EDX analysis with electron or x-ray beam OFF ---> spectrum_a

b) perform EDX analysis with electron or x-ray beam ON ---> spectrum_b.

your net EDX spectrum will be netEDXspectrum = spectrum_b - spectrum_a.

Please take care that the measurement times are equal.

Good luck

Yes I agree with Steven

Thank you Samwel and Joseph for your answers.

Mikhail Demichev could you recommend how to load Pu-Be spectrum to particleGun and which format ?

Agood question and best answer of Nobuyuki Hamada

We can calculate Net count rate uncertainty in gamma spectrometry Technique by using square limit equation, you should calculate the total error ( systematic and theoritical) before calculate Activity of samples

You do not have to take only in consideration the hall-life but also the fact that radioactivity is more diluted. In real life I would add the initial 21 microliters in the smallest total volume and add 2 micrometers one day after calibration date ( written on the recipient) , 4 micrometers 2 days after calibration day, etc....

The detailed answer is complicated. Basically, the stability of nuclides depends on their number of protons/neutrons and some configuration are more stable then others (analogue to electronic configurations in the atom). So it turns out that all configurations with 43 protons either decay in Mo (42) or Ru (44) because both these elements have a lot of stable isotopes.

Iodo-bead which consists of oxidant N-chlorobenzenesulfonamide is better agent then chloramine-T method, because labelling efficiency via idobead is achieve almost 99% while with chloramine-T method labelling efficiency is 90%.

how are you staining? how are you running your samples? these are often the 25kDa light chains.

I follow.......

Bonsoir Monsieur

j apprécie beaucoup votre intervention,

et voudrais avoir une documentation sur ce sujet, même en dehors de mon territoire d’intérêt, si c'est possible bien sure . MERCI

Linear

I would suggest that those of us that care about these issues use appropriate language ourselves. We should not refer to the accidents as "disasters". I am not trying to whitewash the the risks but the three that are always talked about were not disasters in comparison to the deaths that happened with the tsunami is Japan. The tsunami kill almost 20k. The evacuation of people due to radiation phobia killed almost 2k. The nuclear accident killed zero and will probably kill no one in the long run from radiation exposure. We need to tell the truth and stop allowing the anti-nuclear groups to control the dialog and tell lies about what happens when an accident occurs. In no case should we downplay the risks but present them in terms of the risk compared to other risks. We should help other understand what the risks are from using other energy technologies and compare them fairly. Recent studies of experts in various fields show that sometimes the experts don't have the full set of facts and are thus timid to speak out. I was in this group until recently until I took the time to study it out. I now have a very large bibliography of good data to support my statements and I can speak with boldness on these issues. I am glad to share what I have learned. I give public talks on energy technologies and their impacts on society and the environment. So far the talks have been are well received and many people tell me that they appreciate being told the truth so that they can be informed citizens.

tanks, guys!

Is important to show to the mineral industries that to protect the environment is a question of survival for them. Each accident is a disaster for all, i.e, the owners, the population and the environment lose. While the owners do not open their eyes to this problem there will be many catastrophic accidents with their consequences. Technology can help but this never will be enough.

If you want to remove Radium isotopes. There is some recommended methods for removal and separation of radium. Among of these methods, ion exchange and chemical precipitation method as sulphate in presence of barium (as carrier). I wish this answer will help you.

Don't know.

Have a look at reports on human tumour transplant studies in nude mice, e.g. by Petersen et al., or Baumann et al.

W

It's great out of box system experimentation observations!!!!!

Often proof getting hidden in unexpected natural phenomena.....

Excellent answers

I would also propose Anti-ABCA1 (phospho S2054) antibody (ab125064) or

(ab248108) from Abcam

Fahad Ibraheem Almasoud

dose this rule apply to all radionuclides.

Hi Stefania,

We incubate cells at 37°C with radiolabeled antibody and at each time point separate supernatant, cell-bound fraction and cells (internalized fraction) for gamma-counting.

Thnx, Nikolay. I didn't think about this factor at all implying thin wire supplying charge to the ball. But this wire changes completely situation.