Description:• Description of the Prior Art
Internal Dose Uptake
If the source of radiation is inside our body, we say, it is internal exposure. The intake of radioactive material can occur through various pathways such as ingestion of radioactive contamination in food or liquids, inhalation of radioactive gases, or through intact or wounded skin. Most radionuclides will give you much more radiation dose if they can somehow enter your body, than they would if they remained outside. For internal doses, we first should distinguish between intake and uptake. Intake means what a person takes in. Uptake means what a person keeps.

When a radioactive compound enters the body, the activity will decrease with time, due both to radioactive decay and to biological clearance. The decrease varies from one radioactive compound to another. For this purpose, the biological half-life is defined in radiation protection.

The biological half-life is the time taken for the amount of a particular element in the body to decrease to half of its initial value due to elimination by biological processes alone, when the rate of removal is roughly exponential. The biological half-life depends on the rate at which the body normally uses a particular compound of an element. Radioactive isotopes that were ingested or taken in through other pathways will gradually be removed from the body via bowels, kidneys, respiration and perspiration. This means that a radioactive substance can be expelled before it has had the chance to decay.
As a result, the biological half-life significantly influences the effective half-life and the overall dose from internal contamination.
• Objects of the Invention
Measurement of internal radioactive contamination due to gamma emitting radionuclides in human body during normal as well as in emergency situations.

Useful for nuclear facilities involved in handling of High Energy Photon (HEP) (E?>200keV) emitters i.e. fission and activation products. These facilities are nuclear power plants, research reactors, research laboratories, isotope production, reprocessing, waste management, defence etc.
• Summary of the Invention
In health physics, whole-body counting refers to the measurement of radioactivity within the human body. The technique is primarily applicable to radioactive material that emits gamma rays. Alpha particle decays can also be detected indirectly by their coincident gamma radiation.
• Detailed Description of the Invention
We have designed a system which count the person body Dose in 1 minute counting time.
o Features of the SSB-WBC:
? High throughput -monitor ~30 persons per hour.
? One Minute counting time.
? Convenient standing counting geometry.
? 0.3 – 2.0 MeV gamma energy range.
? Two large size Na(Tl) sodium Iodide crystal scintillators housings.
? Lead shielded enclosure with MS covering.
? Easy to assemble and dismantle.
? No moving parts, low maintenance.
? Except sodium Iodide crystal scintillators housings all components are indigenous.
? Rapid assessment of WBC data.
? Accommodate 99% of body dimension of an Indian Adults.
? Information on localized internal contamination can be obtained by analyzing individual sodium Iodide crystal scintillators housing spectrum.

• Efficiency Calibration of SSB-WBC
• Efficiency calibration to be done using reference BOMAB phantom.
• Calibration of the system will be carried out by SSBI, during installation & commissioning as well as later at a fixed periodicity of once in a year.
• Health of the system to be checked daily using disk sources of 137Cs, 60Co
(0-50 kBq strength each).
, Claims:We Claim that:
1. We, S.S.B.I Exports Pvt Ltd has successfully designed, developed & manufactured Walk thru Quick Scan Whole body Counting System under “Make in India”
2. Using “SSB-WBC” Walk thru Quick Scan Whole Body Counting System, we can give assurance to get accurate & desired results of Gamma Spectroscopy as we are using lowback ground very thick walls made up of MS plates and lined with a layer of virgin lead.
3. The system throughput is one person every 2 minutes using a 60-second counting interval. This means that approximately 30 people can be processed in an hour.
4. SSB-WBC used to detect Iodine radioactive source inside the body and outside of body.

We claim that SSB-WBC system can achieve < 150 bq MDA for Cs-137 and Co-60 source in 1 minute sample counting and 1 minute Background counting time.

Resolution:
Resolution factor is an essential parameter needed in peak identification of the obtained spectra in order to qualify and quantify the spectra. The energy resolution of the sodium Iodide crystal scintillators housing is conventionally defined as the full width at half maximum (FWHM) divided by the location of the peak energy.