scholarly journals Dose assessment for NPP staff for beyond design basis accident taking into account typical site infrastructure

2020 ◽  
Vol 64 (4) ◽  
pp. 485-490
Author(s):  
V. I. Orlovskaya ◽  
I. G. Trifonov
Keyword(s):  
Effective Dose ◽  
Radiation Effect ◽  
Dose Assessment ◽  
Internal Exposure ◽  
External Exposure ◽  
Respiratory Protection ◽  
Annual Dose ◽  
Design Basis ◽  
Design Basis Accident ◽  
Total Effective Dose

Assessment of radiation effect on nuclear power plant staff was made for beyond design basis accident (4 hours period). The considered accident scenario includes emergency radionuclide emission through containment bypass. Assessment of radiation effect on NPP staff was done on the basis of radionuclide concentration distribution on site considering typical infrastructure. Concentration mapping was calculated by developed program module for COMSOL 3.5a application. The obtained data included average volume radionuclide activities in lower air layer, total inhalation dose, effective dose of external exposure, equivalent and effective dose in thyroid and total effective dose for NPP staff during beyond design basis accident. Doses from radioactive cloud (external exposure) and from inhalation (internal exposure) were estimated for the following radionuclides: 137Cs, 134Cs, 131I, 133I, 90Sr. In the case of selected beyond design basis accident the total effective dose of staff is 61,98 mSv for the first 4 hours after the accident beginning. This number is slightly above the threshold of the allowable annual dose limit for personnel in emergency situations (50 mSv). Taking into account that short-lived iodine radionuclides 131I и133I give the main contribution in the dose (50.23 mSv including 27.23 mSv for thyroid), such emergency actions as respiratory protection and iodine prophylaxis for the staff can significantly decrease the received doses.

Radiation Dose Evaluation of Typical Design Basis Accident for Advanced PWR in China

2021 ◽  
Author(s):  
Haiying Chen ◽  
Shaowei Wang ◽  
Xinlu Tian ◽  
Fudong Liu
Keyword(s):  
Radiation Dose ◽  
Effective Dose ◽  
Half Life ◽  
Nuclear Power ◽  
Outer Boundary ◽  
Design Basis ◽  
Loss Of Coolant Accident ◽  
Design Basis Accident ◽  
Typical Design ◽  
Total Effective Dose

Abstract The loss of coolant accident (LOCA) is one of the typical design basis accidents for nuclear power plant. Radionuclides leak to the environment and cause harm to the public in LOCA. Accurate evaluation of radioactivity and radiation dose in accident is crucial. The radioactivity and radiation dose model in LOCA were established, and used to analyze the radiological consequence at exclusion area boundary (EAB) and the outer boundary of low population zone (LPZ) for Hualong 1. The results indicated that the long half-life nuclides, such as 131I, 133I, 135I, 85Kr, 131mXe, 133mXe and 133Xe, released to environment continuously, while the short half-life nuclides, such as 132I, 134I, 83mKr, 85mKr, 87Kr, 88Kr, 135mXe and 138Xe, no longer released to environment after a few hours in LOCA. 133Xe may release the largest radioactivity to environment, more than 1015Bq. Inhalation dose was the major contribution to the total effective dose. The total effective dose and thyroid dose of Hualong 1 at EAB and the outer boundary of LPZ fully met the requirements of Chinese GB6249.

EVALUATION OF DOSE IN SLEEP BY MATTRESS CONTAINING MONAZITE

2019 ◽  
Vol 187 (3) ◽  
pp. 286-299
Author(s):  
Bong-Gi Kim ◽  
Kyu-Hwan Jeong ◽  
Hyeong-Ki Shin
Keyword(s):  
Age Groups ◽  
Decay Chain ◽  
Dose Assessment ◽  
Internal Exposure ◽  
External Exposure ◽  
Radon Progeny ◽  
Conversion Factors ◽  
Assessment Program ◽  
Radioactive Concentration ◽  
Effective Doses

Abstract Some companies in Korea have sold beds which contain a processed product containing monazite powder. Consumers may receive external exposure by radiation emitted by progeny radionuclides in uranium and thorium, and internal exposure through the breathing of radon progeny radionuclides produced in the decay chain. Thus, in this study, age specific dose conversion factors (mSv y−1 Bq−1) by external exposure and dose conversion factors by internal exposure (mSv y−1 per Bq m−3) were derived. Besides, a dose assessment program were developed to calculate dose by taking into account real conditions. And the age specific dose was evaluated using the radioactive concentration measured by the NSSC. As a results, external exposure was assessed to get effective doses in the range of 0.00086 to 0.0015 mSv y−1 by external exposure and a committed effective doses in the range of 1.3 to 12.26 mSv y−1 by internal exposure for all age groups.

DETERMINATION OF THE TOTAL EFFECTIVE DOSE OF EXTERNAL AND INTERNAL EXPOSURE BY DIFFERENT IONIZING RADIATION SOURCES

2019 ◽  
Vol 187 (1) ◽  
pp. 129-137
Author(s):  
V A Kudryashev ◽  
D S Kim
Keyword(s):  
Ionizing Radiation ◽  
Effective Dose ◽  
Radiation Risk ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
The Body ◽  
Internal Exposure ◽  
Complex Method ◽  
Radiation Sources ◽  
Total Effective Dose

Abstract The purpose of the research is to develop an integrated technique for determining the effective dose (E) of external and internal exposure by different sources of ionizing radiation. The proposing technique for determining the total effective dose is based on three methods of calculation. The first one is multiplying the value of the individual dose equivalent $H_{p}(10)$ by the factor of 0.642 to account for radiation shielding by various organs and tissues and its backscattering. The second method is multiplying $H_{p}(10)$ by the conversion factor of air kerma in free air in a plate phantom, depending on the photon energy. The third method is multiplying $H_{p}(10)$ by the sum of the radiosensitivity coefficients of various organs and tissues. As a result of research, a complex method was developed for determining the total effective dose, composed of doses of cosmic radiation, external gamma-, beta- and neutron radiation, internal exposure from radionuclides, including CDP of radon and thoron, entering the body through the organs of digestion and respiration. The proposed technique for determining the total effective dose allows one to take into account the comprehensive effect of ionizing radiation sources on a person and to obtain a more accurate measure of radiation risk than the existing methods provide.

Evaluation of External Exposure During Building and Operation of Concrete Bridges Constructions That Reuse the Conditionally Released Steels

2011 ◽  
Author(s):  
Michal Panik ◽  
Vladimir Necas
Keyword(s):  
Effective Dose ◽  
Computer Code ◽  
Concrete Bridges ◽  
Internal Exposure ◽  
Critical Groups ◽  
External Exposure ◽  
Calculation Results ◽  
Effective Doses ◽  
The Subject ◽  
The Individual

This paper presents ongoing results of the project presented at ICEM’10 [1] related to the topics of reusing the conditionally released materials from decommissioning. The subject of the reuse of conditionally released materials in this case is modeling of bridge constructions which reuse the conditionally released steel in the form of reinforcement bars for the concrete bridges. A general approach for the project was presented at ICEM’10. The activities of the project continue in evaluating the individual effective doses from the external exposure based on reused conditionally released steels separately for public and for professionals (the internal exposure will be evaluated in next stages of the project). Evaluated scenarios are related to critical groups of professionals constructing the bridges (worker’s scenarios). The computer code VISIPLAN 3D ALARA 4.0 planning tool was used for the calculation of the individual effective dose for professionals. Various limits of the annual individual effective dose are used for the evaluation of calculation results. The aim of the ongoing modeling is to develop a set of data of maximal radioactivity concentration for individual radionuclides in the conditionally released steel used in the bridges model constructions in order not to exceed the limits for the individual effective dose.

scholarly journals Radiation risk assessment for nuclear power plant staff in different emergency situations

2021 ◽  
Vol 66 (3) ◽  
pp. 378-384
Author(s):  
V. I. Orlovskaya ◽  
A. G. Trifonov
Keyword(s):  
Risk Assessment ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Radiation Risk ◽  
Internal Exposure ◽  
Plant Design ◽  
Emergency Situations ◽  
Design Basis ◽  
Design Basis Accident

The paper presents the results of radiation risk assessment for the staff of a nuclear power plant design during design basis accident (spent nuclear fuel assembly falling on fuel in reactor core or storage pool during refueling operations) and a beyond design basis accident (large leakage of the primary coolant with failure of the active part of the emergency cooling system and complete blackout for 24 h). The assessment is based on state-of-the-art radiation risk models from the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) and the International Commission on Radiological Protection (ICRP). The calculation of risk indicators for occupational exposure of NPP staff in emergency situations was carried out on the basis of data obtained using a computational module created in the COMSOL 5.6 multiphysics software, doses from a radioactive cloud and internal exposure due to inhalation for such radionuclides as 134Cs, 137Cs, 131I, 133I, 90Sr. A feature of this approach is the detailed consideration of the NPP industrial site infrastructure, which allows obtaining a more accurate assessment of the radionuclide air distribution and fallout.

Optimization of radiation exposure for staff using e-controlling devices during radiopharmaceuticals' loading and dispensing procedures in F18-PET/CT daily practice

2018 ◽  
Vol 53 (1) ◽  
pp. 45-50
Author(s):  
C. Peștean ◽  
E. Bărbuș ◽  
M.L. Larg ◽  
D. Piciu
Keyword(s):  
Radiation Exposure ◽  
Effective Dose ◽  
Radiation Protection ◽  
Daily Practice ◽  
Total Activity ◽  
Control Area ◽  
Annual Dose ◽  
Pet Ct ◽  
Total Effective Dose ◽  
Loading Procedure

Background: F18-PET/CT technique has been permanently optimized to ensure the best accuracy and to extend its clinical application. Radiation protection remains an omnipresent aspect of daily practice in F18-PET/CT. Introduction: We tried to demonstrate the usefulness of remotely controlled radiopharmaceutical dispensers with smart-phones or tablets in the optimization of staff exposure. Material and methods: We performed a study to evaluate the exposure during loading and dispensing of radiopharmaceuticals working in two different ways: according to the user's manual of the automatic dispenser and, respectively, with an e-controlling application. We calculated the maximal radiation exposure and analyzed the differences related to the annual effective dose. Have been considered 40 loading and 353 dispensing procedures. During the loading, it has been manipulated a total activity of 9348.8 mCi (345905.6 MBq) FDG. A total activity of 2622.5 mCi (97032.5 MBq) FDG has been manipulated during dispensing. Results: The effective dose resulted from the loading procedure measured at the dispenser contact was 445.05 µSv. The effective dose measured in the remote control area during the loading procedure was 0.34 µSv, having a difference of 444.71 µSv. The total effective dose during dispensing procedures measured at the dispenser was 206.6 µSv and the total effective dose measured in the controlling room was 2.64 µSv, thus a difference of 203.96 µSv. The cumulative difference between the effective doses was of 648.67 µSv. Discussion: E-controlling the dispenser, we got an exposure saving representing 61.2% from the operator's annual dose. Conclusions: This study demonstrates the effectiveness of e-controlling devices in radiation protection of the staff working in F18-PET/CT.

scholarly journals Alpha Spectrometry of Radon Short-Lived Progeny in Drinking Water and Assessment of the Public Effective Dose: Results from the Cilento Area, Province of Salerno, Southern Italy

Materials ◽  
2020 ◽  
Vol 13 (24) ◽  
pp. 5840
Author(s):  
Enver Faella ◽  
Simona Mancini ◽  
Michele Guida ◽  
Albina Cuomo ◽  
Domenico Guida
Keyword(s):  
Drinking Water ◽  
Effective Dose ◽  
Health Hazard ◽  
Age Groups ◽  
Internal Exposure ◽  
Threshold Values ◽  
Campania Region ◽  
Radon Activity ◽  
National Regulation ◽  
South Italy

Radon is a naturally occurring radioactive gas present in the hydrosphere, lithosphere and atmosphere abundantly. Its ionizing radiation provides the largest human internal exposure by inhalation and ingestion to natural sources, constituting a serious health hazard. The contribution to total exposure is mainly due to inhalation, as ingestion by food or drinking water is typically very small. However, because of public health concerns, the contributions from all these sources are limited by regulations and remedial action should be taken in the event that the defined threshold values are overcome. In this paper, the first campaign of measurements to control the radon activity concentration in drinking water from public water supplies in the province of Salerno, south Italy, is described. The results represent a main reference for the area, as it was never investigated before. The purpose of this survey was to contribute to data compilation concerning the presence of radon-222 in groundwater in the Campania region and to determine the associated risk for different age groups. The maximum radon activity concentrations and the related total annual public effective dose turned out to be lower than the threshold values (100 Bq/l and 0.1 mSv/y, respectively) indicated by international guidelines and the national regulation, showing that the health risks for public consumption can be considered negligible.

scholarly journals Radon Activity Concentrations in Natural Hot Spring Water: Dose Assessment and Health Perspective

2021 ◽  
Vol 18 (3) ◽  
pp. 920
Author(s):  
Eka Djatnika Nugraha ◽  
Masahiro Hosoda ◽  
June Mellawati ◽  
Untara Untara ◽  
Ilsa Rosianna ◽  
...  
Keyword(s):  
Public Health ◽  
Effective Dose ◽  
Radiation Protection ◽  
Water Samples ◽  
Hot Springs ◽  
Hot Spring ◽  
Annual Effective Dose ◽  
Spring Water ◽  
Dose Assessment ◽  
West Java

The world community has long used natural hot springs for tourist and medicinal purposes. In Indonesia, the province of West Java, which is naturally surrounded by volcanoes, is the main destination for hot spring tourism. This paper is the first report on radon measurements in tourism natural hot spring water in Indonesia as part of radiation protection for public health. The purpose of this paper is to study the contribution of radon doses from natural hot spring water and thereby facilitate radiation protection for public health. A total of 18 water samples were measured with an electrostatic collection type radon monitor (RAD7, Durridge Co., USA). The concentration of radon in natural hot spring water samples in the West Java region, Indonesia ranges from 0.26 to 31 Bq L−1. An estimate of the annual effective dose in the natural hot spring water area ranges from 0.51 to 0.71 mSv with a mean of 0.60 mSv for workers. Meanwhile, the annual effective dose for the public ranges from 0.10 to 0.14 mSv with an average of 0.12 mSv. This value is within the range of the average committed effective dose from inhalation and terrestrial radiation for the general public, 1.7 mSv annually.

MEASUREMENT OF THE ACTIVITY CONCENTRATIONS OF GAMMA EMITTING RADIONUCLIDES IN TOOTHPASTE SAMPLES AND ASSESSMENT OF THE CORRESPONDING ANNUAL EFFECTIVE DOSES

2021 ◽  
Author(s):  
Anas M Ababneh ◽  
Qutad M Samarah
Keyword(s):  
Effective Dose ◽  
Oral Hygiene ◽  
Annual Effective Dose ◽  
Daily Basis ◽  
Dose Assessment ◽  
Accidental Ingestion ◽  
Activity Concentrations ◽  
Effective Doses

Abstract It is inevitable that we are exposed to radiation daily from various sources and products that we consume on daily basis. The use of toothpaste for oral hygiene is one of the most common daily practices by humans and yet very little data are available regarding its radiation content. In this work, we investigated the concentrations of gamma emitting radionuclides in toothpaste samples consumed in Jordan. 40K and 226Ra were detected in almost one-third of the samples, whereas 228Ra was detected in nearly half of them. The corresponding activity concentrations in the detected samples were in the ranges of 68.7–154.2, 4.6–14.1 and 1.3–10.0 Bq/kg, respectively. Dose assessment of accidental ingestion of toothpaste for children and adults was made, and its contribution to the annual effective dose was found to be very minimal with maximum doses of ~2.9 and 1.3 μSv for children and adults, respectively.

Sign in / Sign up

Export Citation Format

Share Document