Survey Meter Research Articles

Spatial mapping and radiometric survey of high background radiation areas in Southern Tamil Nadu, India

Southern Tamil Nadu has placer deposits, which is rich in minerals like zircon, garnet, monazite and rutile containing with radionuclides of U, Th and their decayed products. The present study is to identify the high background radiation areas in the regions of South west–east coast of Tamil Nadu. The ground radiometric survey was conducted in different seasons using portable radiation survey meter and global positioning system. Total of 137 observation spots were marked from 5 blocks for repeat measurements. Then calculated for the outdoor effective external terrestrial dose to the public residing in these blocks. The survey found average absorbed dose rate of block in this order 3>2> 4>1>5 (1394, 641, 247, 225, 167 nGy/h, respectively). From the data, a spatial mapping was performed for seasonal variation and interpolated for the unknown areas of dose rate. The outdoor effective dose to the public was found to be 1.66> 0.79>0.31>0.27>0.20 mSv/y with respective blocks. Conclusion: The dose to public was found to be lower, when compared with other high background radiation areas in the world. Therefore, there is no significant radiological risks to the public from natural radiation exposure.

Pattern of radiation safety measures and security culture in four major hospitals, Ismailia, Egypt

Background: Radiation safety and radioactive source security constitute an essential part of radiation protection in medicine, and launching them involves cultural interactions.Aim: To explore the current situation of radiation protection in hospitals in order to improve radiation safety and security culture and measures in Ismailia city hospitals.Subjects and Methods: A cross sectional study was conducted at 13 units in four hospitals in Ismailia city. Health care workers (292) with potential exposure to radiation (physicians, technicians, nurses and physicists) were included. Safety culture questionnaire, inspection checklist and thermo scientific model survey meter to assess the radiation levels in different units were used.Results: The results of this study showed moderate radiation safety culture (The mean scores culture was 95.3±12.8). The linear regression analysis showed that working days/week significantly predicts the safety culture of participants. Radiation safety and security measures represented in different departments were insufficient. There was variability among hospitals and departments as regard the level and the efficiency of protection, concerning shields and protection of doors and windows.Conclusion: Different departments/ units in the investigated hospitals showed an overall inadequacy of radiation safety and security measures and most of them showed inefficiency of protection as well as the design of rooms.

STUDIES ON GAMMA DOSE RATES IN INDOOR AND OUTDOOR ENVIRONMENT OF HASSAN CITY, KARNATAKA.

Gamma-ray dose rates have been measured in the indoor and outdoor air of Hassan City. The measurements were done from 25 locations of Hassan City at 1m above the ground surface for radiometric, geophysical and environmental surveys using a lightweight portable radiation survey meter (scintillometer). The meter reading fluctuates around a mean value and is proportional to the count rate detected by the unit. This is because of the random nature of radioactivity. In the present study, the absorbed gamma dose rates in indoor and outdoor air varies from 69±2 to 481±18 nGy h-1 with a geometric mean of 180±6 nGy h-1 and 20±0 to 371±14 nGy h-1 with a geometric mean of 107±3 nGy h-1. The annual effective gamma dose rates in indoor and outdoor air varies from 0.34 to 2.36mSv y-1 with a geometric mean of 0.88mSv y-1 and 0.02 to 0.45mSv y-1 with a geometric mean of 0.12mSv y-1. The gamma dose rates of Hassan City is higher compared to the world average value and lower when compared to other locations of India.

Assessment of Nuclear Moisture Density Gauges at a Secondary Standard Dosimetry Laboratory in Ghana during December 2015–December 2017

Introduction: Nuclear moisture density gauges are widely used in construction industry in different countries across the world, including Ghana, on a large scale. Like all irradiating devices, the nuclear gauges should be subjected to radiation safety assessment based on radiation protection and safety principles. Regarding this, the objective of this research was to investigate the radiation safety of the nuclear moisture density gauges to ensure the absence of any leakages from the radioactive source. Material and Methods: For the purpose of the study, a survey meter (RADOS-120) was used to measure and record the radiation dose once at a distance of 1 m from the surfaces of all sides of the nuclear moisture density gauge and very close distance from the surfaces of the device. Moreover, the device was examined using radiation contamination test and counts on a standard block. Results: A total of nine nuclear moisture density gauges manufactured by Troxler Electronics Inc. in the USA were evaluated within a period of 3 years. The minimum and maximum average dose rates were 0.49 and 66.67 μSv/h, respectively. The highest and lowest average dose rates were recorded in 2017 and 2016 on the devices with serial numbers of 38260 and 32839, respectively. Conclusion: The assessment of the nuclear moisture density gauges under study revealed noradiation contamination leakage. Furthermore, all the evaluated gauges were shown to function properly and were safe for the intended purposes.

Measurement of terrestrial gamma radiation dose rate and radioactivity levels in the southern hilly regions of Manipur, India

The terrestrial gamma radiation levels and associated dose rates were estimated at 120 different sites with 12 soil samples in the southern hilly regions of Manipur, India, consisting of Churachandpur and Chandel district, by using NaI (Tl) scintillator-based Micro-R survey meter and high-purity germanium detector. The observed annual effective dose in this study area ranges from 0.37 to 1.51 mSv/y, with a mean value of 0.85 ± 0.16 mSv/y. Whereas Churachandpur and Chandel districts showed a mean value of 0.88 ± 0.18 (ranges: 0.67 to 1.51) mSv/y and 0.83 ± 0.14 (ranges: 0.37–1.24) mSv/y, respectively. This southern region of Manipur shows slightly higher values of annual effective dose as compared with the earlier reported value of about 0.7 mSv/y for the central valley region of Manipur, and world average value of about 0.4 mSv/y, reported by United Nations Scientific Committee on the Effects of Atomic Radiation (2000). The soil analysis for226Ra,232Th, and40K of this area gives an average activity concentration of 44.3 (ranges: 23.8–78.6) Bq/kg, 169.1 (ranges: 83.6–305.1) Bq/kg, and 1489.1 (ranges: 752.5–2426.8) Bq/kg, respectively.

Reduction of Operator Exposure Radiation Dose and Evaluation of Image Quality Using Half Scan in CT Fluoroscopy

In recent years, the number of examinations and treatments using computed tomography fluoroscopy (CTF) has been increasing, and there is concern about an increase in the exposure radiation dose of the operator. Use of half scan CTF can be expected to reduce the exposure radiation dose, but there is no report. The purpose of this study was to evaluate the exposure radiation dose at the operator's position and image quality when using a half scan CTF. The left side facing the gantry was the operator's position, and the ambient dose equivalent at 160 cm, 130 cm, and 100 cm from the floor was measured using an ionization chamber survey meter. The absorbed dose at the forceps holding position of the operator was measured using a fluorescent glass dosimeter with the forceps holding position 15 cm caudal from the scan center. The imaging conditions used a tube voltage of 120 kV and a tube current of 50 mA. Half scan CTF was performed by changing the center angle of the half scan on the console every 45°. As a result, the set angles were 135°and 90°at the operator's position, and 135°at the operator's forceps holding position. In addition, we evaluated the effect of half scan CTF on image quality. CTF images were collected with a cryogenic needle used for cryotherapy punctured in a water-equivalent self-made phantom. The profile curves of the obtained images were drawn and compared using analysis software to evaluate the effects of artifacts. Then, the SD of the CT value of the region of interest with and without the artifact was measured, and the relative artifact index was calculated and evaluated. Using the same image, CT value and SD were tested to evaluate noise. Half scan CTF had no effect on the image quality due to artifacts and noise.

Verification for utilization method based on the image of Geiger-Mueller survey meter

Verification for utilization method based on the image of Geiger-Mueller survey meter

A TECHNOLOGY OVERVIEW OF ACTIVE IONIZING RADIATION DOSEMETERS FOR PHOTON FIELDS.

Radiation protection and radiation dosimetry strongly rely on measurements performed by dosimetry instrumentation. Two categories of dosimetry instrumentation prevail: personal dosemeters and survey meters. Passive dosemeters were for many years the base of personal and area dosimetry (environmental, including workplace). Survey meters have been long-established between area meters due to their dose rate measurement capability, but just over a decade ago, debates over possibility that electronic personal dosemeters (EPDs) could replace passive personal dosemeters as legal monitoring devices have started. These debates have now branched into the use of EPDs, but also survey meters in various exposure scenarios, where some concerns have been reported. These concerns were mostly related to the response in pulsed X-ray fields and poor energy response. This article summarizes recent literature related to electronic dosemeters for strongly penetrating photon radiation and covers technologies used in contemporary EPDs and survey meters, their performance and future perspectives.

Risk Assessment of Public Gamma Radiation in Some Provinces of Iran

Introduction: Humans are continuously exposed to ionizing radiation. In order to evaluate health hazards, the measurements of background radiation in most countries have special importance. Material and Methods: The measurements were carried out by an Ion Chamber Survey Meter (X5C plus), during daylight in 2016. The collected and reported data were based on two ways. Firstly, the measurements of gamma background radiation were performed directly in indoor and outdoor places of five areas, including north, south, west, center, and east, in 11 cities of South Khorasan province, Iran. Secondly, the related data of other studies were used for several provinces of Iran. Results: According to the obtained results, the maximum and minimum of annual effective gamma dose were 0.72 and 0.34 nSvh-1 in Asadabad and Tabas, Iran, respectively. The maximum and minimum of annual effective gamma dose were 0.84 and 0.27 nSvh-1 in Hamedan, as well as Chaharmahal and Bakhtiari, Iran, respectively. Conclusion: The average values of the annual effective dose and estimated excess lifetime cancer risk (ELCR) were 0.60 nSv and 2.11×10-3, respectively, which were higher than the amounts of the world average. The calculated ELCRs for all Iran provinces were higher in comparison to the world average value of 0.25×10-3.

Evaluation of scattered radiation from fluoroscopy using small OSL dosimeters.

Recently, there has been a significant amount of interest in studying the importance of radiation doses to the eye lens during endoscopic retrograde cholangiopancreatography (ERCP). A study that focused on measuring the scattered radiation using an ionization chamber survey meter reported that a lead curtain was useful in reducing the scattered radiation. The over-couch X-ray tube system tends to deliver higher doses to the head and neck of the staff involved in the procedure than the under-couch X-ray tube position. In this study, a small optically stimulated luminescence (OSL) dosimeter called the nanoDot was used to evaluate and measure the amount of radiation; this dosimeter was developed by Landauer Ltd. and was specifically designed for point measurements. There are numerous studies that have reported the usefulness of personal OSL dosimeters other than the nanoDot to measure scattered radiation. Here, we evaluated the amount of scattered radiation, along with the degree of reduction achieved with the use of a protective curtain, while employing a personal OSL dosimeter and nanoDot. When the scattered radiation dose was measured using the nanoDot, the maximum recorded value without a protective curtain was 0.363mGy and that with a protective curtain was 0.026mGy, both at the height of 100cm. The maximum reduction rate of scattered radiation while using a protective curtain was approximately 93% and 97% at 100cm and 150cm, respectively. The measured values recorded using both personal OSL dosimeters and nanoDot machine were strongly correlated.

Development of Simple Methods to Reduce the Exposure of the Public to Radiation from Patients Who Have Undergone 18F-FDG PET/CT.

At a time when reducing the radiation dose to patients and the public has become a major focus, we assessed the radiation exposure rate from patients after an 18F-FDG PET/CT scan and evaluated different interventions to reduce it. Methods: We enrolled 100 patients, divided into 2 groups. For both groups, the radiation dose rate was measured with an ionization survey meter immediately after the scan. For group 1, the patients then voided and their dose rate was measured again. For group 2, the patients waited 30 min before voiding, and we measured the dose rate before (group 2A) and after (group 2B) they voided. Results: In total, 74 of the 100 patients exceeded the 20 μSv/h (2 mR/h) threshold immediately after the scan. In group 1, the mean dose rate decreased by 20.0% from the postscan measurement, with 12 of 36 remaining at or above 20 μSv/h. In group 2A, the mean dose rate decreased by 23% from the postscan measurement, with 9 of 38 remaining at or above 20 μSv/h. In group 2B, the mean dose rate decreased by 35% from the postscan measurement, with 1 of 38 remaining at 20 μSv/h. Conclusion: Nearly 75% of patients undergoing an 18F-FDG PET/CT scan exceed 20 μSv/h when leaving the imaging facility. The most effective method to reduce radiation exposure was to have the patient void 30 min after the examination.

Estimation of ambient gamma radiation dose and drinking water radon concentration in coastal taluks of Uttara Kannada district, Karnataka

This study assesses the ambient gamma dose rate and radon concentration in drinking water at different locations in few coastal taluks of Uttara Kannada district. The ambient gamma dose and 222Rn activity in drinking water has been estimated by using micro R survey meter and Emanometry technique respectively. The annual effective doses ranges from 0.39 to 0.82 mSvy−1 with a geometric mean value of 0.55 mSvy−1 and it is slightly higher than the world average value. 222Rn activity in drinking water vary from 3.34 ± 0.22 to 160.18 ± 1.84 Bql−1 with mean value of 25.07 ± 0.86 Bql−1. Annual average ingestion dose due to consuming water are well below the WHO and EC suggested action level of 100 µSvy−1.

Mercury solubility measurements in natural gas components at high pressure

Saturated vapor pressure of elemental mercury (Hg) and Hg solubility in compressed gaseous methane, ethane, and carbon dioxide were investigated. The apparatus designed for this study was based on a flow method and equipped with a cold vapor atomic absorption survey meter to measure Hg concentration in gas phase. The saturated Hg vapor pressure ranged from 4.579 × 10−2 to 2.757 × 10−1 Pa at 278–298 K. The Hg solubility was measured up to 6.042 MPa for methane, 3.533 MPa for ethane, and 2.070 MPa for carbon dioxide at 268–303 K. The Hg mole fraction ranged from 4.842 × 10−9 to 8.683 × 10−7 in the vapor phase. The Hg solubility decreases with increasing pressure, and the pressure dependencies are similar in the three gases. The activation energy of Hg solubility was determined from the Arrhenius plot at the 1.55 and 3.55 MPa isobars. The activation energy at 1.55 MPa is about 60 kJ/mol·K for the three gases, similar to that at the saturated Hg vapor pressure. At 3.55 MPa the activation energy has the same value for methane but decreases to around 60 kJ/mol·K for ethane. The Peng–Robinson equation of state (PR-EOS) was used to correlate the saturated Hg vapor pressure and the Hg solubility in the vapor phase. The attractive parameter in the PR-EOS was fitted with the saturated Hg vapor pressure, and its temperature dependence was investigated using the van der Waals one-fluid mixing rule. The average absolute deviations were 0.322, 0.265 and 0.197 % for Hg solubility in gaseous methane, ethane and carbon dioxide, respectively. This investigation contributes to predicting mercury partitioning in natural gas processing facilities.

Investigation of conventional diagnostic X-ray tube housing leakage radiation using ion chamber survey meter in Mizoram, India

Leakage radiation that transmitted the protected X-ray tube housing was measured and compared with national and international safety standard. To the best of the authors’ knowledge, no tube housing leakage measurement has been done so far in the present study area. The authors considered all the conventional diagnostic X-ray units in Mizoram, India. Ion chamber survey meter was used to measure leakage radiation and it was placed at 5 different positions (left, right, front, back, top) of the X-ray tube. Measurements were done at 1 m focus-to-detector distance by projecting X-ray tube vertically downward with collimator diaphragms closed completely. SPSS statistics for windows, version 17.0 (SPSS, Inc., Chicago, IL, USA) was used to derived mean, standard error of the mean etc. The tube housing leakage exposure rates ranged between 0.03 mRh-1 and 500 mR h-1; among the 5 positions, rate measured in the front direction has the highest mean at 41.61±8.63 mR h-1; whereas the top has the lowest 4.57±1.16 mRh-1. Tube housing radiation level ranged from 0.01 to 58 mR in one hour. Leakage radiation was minimum at the top position of the tube and maximum in the front direction. All the equipment were in compliance with national and international standard norms, the highest leakage radiation level was 50.43% of the safety limit.

Correlation of Radiocesium Activity between Muscle and Peripheral Blood of Live Cattle Depending on Presence or Absence of Radiocontamination in Feed.

To monitor radiocesium activity in skeletal muscle of live cattle, the animals were given radiocesium-contaminated feed continuously, then switched to contamination-free feed after radiocecium concentration in peripheral blood (PB) reached plateau. Radioactivity in skeletal muscles of neck and rump was measured by attaching the probe of a NaI survey meter closely on the body surface just above the muscle of the live cattle (external measurement). We validated the strong positive correlation between the value of the external measurement and radiocesium activity concentration of dissected muscle (r = 0.89, P < 0.001 for neck; r = 0.80, P < 0.001 for rump). Accumulation of radiocesium both in muscle and PB was proportional to the total amount of radiocesium cattle ingested. However, radioactivity concentration in PB was constant in the cattle that had continuously ingested radiocesium, lower than 2.0 × 105 Bq in total within 67 days from the beginning of radiocesium intake. In addition, the ratio of radiocesium activity in muscle to that in PB was lower during the time when radiocontaminated feed was ingested than that of contamination-free feed ingestion. Using the correlation of radioactivity between muscle and PB, we confirmed that a majority of the cattle in the ex-evacuation zone of the Fukushima Daiichi nuclear power plant accident, from 167 to 365 days after the accident occurred, were in the declining period of radiocesium intake.

Clinical effects of expanded super-thin perforator flaps in the shoulder, neck, and chest in reconstruction of extensive burn scars in the face

Objective: To explore the clinical effects and key techniques of expanded super-thin perforator flaps in the shoulder, neck, and chest in reconstruction of extensive burn scars in the face. Methods: From January 2008 to November 2018, 22 patients with extensive burn scars in the face were admitted to the Department of Plastic Surgery of Dongguan Kanghua Hospital and the Department of Plastic Surgery of Dermatology Hospital of Southern Medical University, with 3 males and 19 females, aged from 4 to 48 years. There were 16 cases of type Ⅱ and 6 cases of type Ⅲ in facial scars. Before the first stage of expansion surgery, Doppler blood flow survey meter or multi-slice CT was used to locate the perforator vessels. One to four expanders with rated capacity ranged from 100 to 600 mL were placed in the patients. We gave 20% to 30% of the rated capacity of expander intro-operation and common injection with 10% to 15% of the rated capacity of expander per week post-operation until the volume reached 1.5 to 2.5 times of the rated capacity of expander during the past 3 to 4 months. At the second stage of surgery, the perforators were located again before surgery with the same method. The size of defects after the excision of facial scars ranged from 6 cm×4 cm to 18 cm×16 cm. With perforators used as nutrient vessels, narrow pedicle flaps or random flaps ranging from 6 cm×6 cm to 22 cm×18 cm were elevated as rotating or advancing to reconstruct the defects. The donor sites were sutured directly. Some of the flaps needed stage Ⅲ operation for cutting the pedicle. The survival of flaps, post-operation complications, and follow-up were assessed. Results: All flaps of 22 patients survived. All the donor sites were closed simultaneously. One patient underwent an additional surgery for 5 cm×4 cm necrosis on distal part of flap caused by subcutaneous hematoma. Two patients with epidermis blister on the flaps were healed by themselves after dressing change. Due to rapid expansion, blood capillary proliferation appeared on the central part of the flap in 3 cases, after slowing down the expansion speed properly, which had no impact on flap transfer. No ischemia or venous congestion phenomenon were observed in the other flaps. During follow-up of 5 to 48 months, the flaps of patients showed no significant bloated appearance, with good complexion and texture, and even could reproduce facial fine-grained expressions naturally. Conclusions: For the reconstruction of extensive burn scars in the face, expanded super-thin perforator flaps can not only acquire large and thin flaps with high matching degree surface skin defect, but also reproduce facial fine-grained expressions. It is a simple and safe method which conforms to the facial aesthetic standard.

Simplified virtual reality training system for radiation shielding and measurement in nuclear engineering

We developed a virtual reality implementation with a virtual survey meter for training and other purposes so that general scientists can utilize virtual reality in nuclear engineering. To demonstrate the efficacy of the implementation, we considered a simplified training scenario that enables beginners and non-experts to experience the environment of radiation sources and radiation shielding walls. Although it is a very simple system compared with operations at an actual facility, it provides a starting point for introductory training in radiation shielding. With comprehensive radiation training in mind, we used a commodity virtual-reality device and the software environments HTC VIVE, Unity, and VRTK. Previous studies confirmed the validity of the point kernel approximation to estimate the dose rate from barrels of nuclear deposits of radiation sources. In this study, we introduced the use of steel and concrete walls as shields in order to establish the training scenario. The virtual survey meter, walls, and barrels were simply created as Unity native objects and could be moved by a hand device through VRTK. Radiation rates were calculated using a short code based on the point kernel method. We verified the r−2 rule and sum rule. As a training scenario, we examined the training to measure the change in radiation dose rate from three barrels when moving the shielding walls. The training scenario was analyzed to show the validity and future applications of our virtual-reality implementation.

Estimation of Radiation Exposure to Workers During [18F] FDG PET/CT Procedures at Molecular Imaging Center, Oman

Positron-emission tomography (PET) is the imaging modality of choice in oncology. In addition, there are several indications for using PET in cardiology and neurology. The main radiotracer used is the radiolabeled glucose analog [18F] fluorodeoxyglucose ([18F] FDG). The high-energy annihilation radiation from positron emission may lead to significant radiation exposure to medical imaging professionals such as technologists and staff nurses, patients, and direct acquaintances of the patient. In this cross-sectional observational study, the effective dose to workers in the Molecular Imaging Center from patients injected with [18F] FDG is assessed. Dose rates were estimated by a calibrated, portable gamma-ray survey meter at 0.3, 0.5, 1.0, and 2.0 m from 70 patients who underwent whole body [18F] FDG PET/CT procedure immediately and 2 hours post-injection. Electronic personal dosimeters were used to determine the radiation doses per PET/CT imaging for the five staff who directly involved in handling of the injected patients. The staff includes two technologists, two staff nurses, and one medical physicist. The mean dose rates from patients after injection and standard deviation (μSv/h) for the four distances were 98.1 ± 20.0, 55.3 ± 20.0, 28.2 ± 10.0, and 10.8 ± 5.0, respectively. After 2 hours, the measurements significantly dropped to 45.7 ± 10.0, 23.6 ± 10.0, 9.9 ± 4.0, and 3.7 ± 1.0 μSv/h. The average effective dose values for a technologist from injected patients throughout the procedure of PET/CT study was 4.17 μSv per study or 5 mSv/y. This is less than the annual limit recommended by the International Commission on Radiological Protection of 20 mSv/y received in the medical imaging profession.

Evaluation of radiation doses at diagnostic X-ray control panels and outside patient entrance doors in Aizawl district, India.

The purpose of this research was to measure the radiation level and estimate the dosage at the control panel (CP) and outside the patient entrance door (PED) of diagnostic X-ray installations. This is important for ensuring the safety of workers and the public, particularly in the study area, where there is no proper radiation monitoring service. A water phantom, 10-L fresh water in a plastic container, was used as the source of scattered radiation. Using an ion-chamber survey meter, the stray radiation rate was measured at the CP and outside the PED for both chest and couch missions. The CPs were fully covered by a protective barrier, providing a negligible exposure rate (i.e., 0.07-4.2mR/h for chest and 0.21-3.8mR/h for couch). By contrast, installations that did not properly cover the CP showed relatively high exposures (from 18 to 205mR/h for chest and 2.4-270mR/h for couch). The radiation rates outside the PED in installations having lead-lined doors were negligibly low; whereas, in installations having no lead-lining, exposure rates reached as high as 95 and 110mR/h for chest and couch missions, respectively. The occupational doses were well below the Atomic Energy Regulatory Board dose limit (i.e., 40mR/week). However, excessive doses were observed in public spaces outside the PED, compared with the dose limit for the public (i.e., 2mR/week).

Ambient neutron and photon dose equivalent H*(10) around a pencil beam scanning proton therapy facility.

To measure leakage ambient dose equivalent H*(10) from stray secondary neutron and photon radiation around proton therapy (PT) facility and evaluate adequacy of shielding design. H*(10) measurement were carried out at 149 locations around cyclotron vault (CV), beam transport system (BTS) and first treatment room (GTR3) of a multiroom PT facility using WENDI-II and SmartIon survey meter. Measurement were performed under extreme case scenarios wherein maximum secondary neutrons and photons were produced around CV, BTS and GTR3 by stopping 230MeV proton of 300nA on beam degrader, end of BTS and isocenter of GTR3. Weekly time average dose rate (TADR) were calculated from H*(10) value measured at selective hot spots by irradiating actual treatment plans of mix clinical sites. The maximum total H*(10) were within 2 µSv/hr around CV, 5 µSv/hr around outer wall of BTS which increases up to 62 µSv/hr at the end of inside BTS corridor. Maximum H*(10) of 20.8 µSv/hr in treatment control console (P125), 23.4 µSv/hr behind the common wall between GTR3 and GTR2 (P132) and 25.7 µSv/hr above isocenter (P99) were observed around GTR3. Reduction of beam current from 6 to 3 nA and 1 nA at nozzle exit lead to decrease in total H*(10) at P125 from 20.8 to 11.35 and 4.62 µSv/hr. In comparison to extreme case scenario, H*(10) value at P125, P132 and P99 from clinically relevant irradiation parameters were reduce by a factor ranging from 8.6 for high range cube to 46.4 for brain clinical plan. The maximum weekly TADR per fraction was highest for large volume, sacral chordoma patient at 8.5 µSv/hr compare to 0.3 µSv/hr for brain patient. The calculated weekly TADR for 30 mix clinical cases and 15 fractions of 1 L cube resulted total weekly TADR of 83-84 µSv/hr at P125, P132 and P99. The maximum annual dose level at these hot spots were estimated at 4.37 mSv/Yr. We have carried out an extensive measurement of H*(10) under different conditions. The shielding thickness of our PT facility is adequate to limit the dose to occupational worker and general public within the permissible stipulated limit. The data reported here can bridge the knowledge gap in ambient dose around PT facility and can also be used as a reference for any new and existing proton facility for intercomparison and validation. First extensive investigation of neutron and photon H*(10) around PT facility and can bridge the knowledge gap on ambient dose.