Health Phys. Abstracts，Volume 122,Number 6

DevelopmentandValidationofaNewDomesticSoftwareforDoseAssessmentduringNormalandAccidentConditionsinNuclearPowerPlants(NPPS)

Ali Haghighi Shad1, Darioush Masti2, Mitra Athari Allaf1, Kamran Sepanloo3, Seyed Amir Hossein Feghhi4

(1.Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran;2. Department of Nuclear Engineering, Bushehr Branch, Islamic Azad University, Boushehr, Iran;3. Reactor and Nuclear Safety School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran;4. Department of Radiation Application, Shahid Beheshti University, Tehran, Iran)

Abstract:In this research, a comprehensive code called KIANA is developed based on the Gaussian plume model to simulate and predict the radiological consequences received through all the possible, reasonable, probable, and standard exposure pathways for NPPs and chemical facilities. To validate the KIANA code, a case study is modeled for Bushehr Nuclear Power Plant Unit One (BNPP-1), and the KIANA code results are compared with the results of the Final Safety Analysis Report (FSAR-2017) data of BNPP-1. To assess the performance of the KIANA code, the total dose due to the airborne pathway in accident conditions including small break LOCA (SBLOCA), large break LOCA (LBLOCA), and equivalent exposure dose for the thyroid gland of a group of infants and children age 1 to 8 y at BNPP-1, are investigated. The KIANA code results show that the total effective doses do not exceed the regulatory limit of 5 mSv for external and internal exposures and the regulatory limit of 50 mSv for thyroid equivalent dose. The KIANA code results indicate good agreement with the results of FSAR-2017.

Keywords: exposure; radiation; health effects; modeling; dose assessment; power plant; nuclear

Health Phys. 122(6):651-662; 2020

EffectsofaModifiedChitosanCompoundCombinedwithLungLavageafterInhalationofDepletedUraniumDust

Yao Xiao1, Feng Zeng1, Weilin Fu1, Yi Zhang1, Xiangyu Chen1, Yi Liang2, Rong Li3, Minghua Liu1

(1.Emergency Department, The Southwest Hospital of Third Military Medical University, Chongqing, China;2. Emergency Department, The General Hospital of Western Theater Command of PLA, Chengdu, China;3. Institute of Combined Injury, College of Preventive Medicine, Third Military Medical University, Chongqing, China)

Abstract:When exposed to depleted uranium (DU), the respiratory tract is the main route for DU to enter the body. At present, lung lavage is considered to be a method for removing DU from the lung. However, there is still room for improvement in the efficiency of lung lavage. In this work, a model of DU dust inhalation injury was established in beagle dogs so that chitosan-diethylenetriaminepentaacetic nanoparticles (CS-DTPA NP) could be synthesized. The purpose of this work was to evaluate the removal efficiency of CS-DTPA NP combined with lung lavage in dogs. Results showed that 7 d after DU exposure, the diethylenetriaminepentaacetic (DTPA) and CS-DTPA NP groups showed lower U content in kidney tissue compared with the normal saline (NS) group. In the left lung tissue (lavage fluid and recovery rate of lavage fluid), the U content in the CS-DTPA NP group was higher than in the NS and DTPA groups. In terms of blood levels, the CS-DPTA NP group increased over time at 1, 3 and 7 d of DU exposure without lavage; however, the U levels in the 3 and 7 d lavage groups were significantly lower than in the non-lavage groups. IL-1 in the lavage fluid of the CS-DPTA NP and CS NPs group were lower than in the NS group. In summary, after respiratory exposure to DU, early inhalation of CS-DPTA NP may block insoluble DU particles in the lung, and if combined with lung lavage, the clearance efficiency of DU from lung tissue improves.

Keywords: aerosols; DTPA; kidneys; lungs; human

Health Phys. 122(6):663-672; 2022

ModelingaLossyDieletricPolymer-basedThermoacousticHighPowerMicrowaveDirectedEnergyExposureDetectionSystem

James J. Frey1, Richard G. Cobb2, John W. McClory1

(1.Department of Engineering Physics, Air Force Institute of Technology, 2950 Hobson Way, Wright-Patterson Air Force Base, OH 45433;2.Department of Aeronautics and Astronautics, Air Force Institute of Technology, 2950 Hobson Way, Wright-Patterson Air Force Base, OH 45433)

Abstract:Presented are design considerations for a potential detection and measurement technique that could provide operational awareness of high power microwave (HPM) directed energy weapon exposure for force health protection applications, leveraging thermoacoustic (TA) wave generation as the field interaction mechanism. The HPM electromagnetic frequency (EMF) regime, used in applications in both the counter-materiel and non-lethal counter-personnel design space, presents real-time personnel exposure warning challenges due to the potentially wide variation in time and frequency domain characteristics of the incident beam. As with other EM-thermal interactions, the thermoacoustic wave effect provides the potential to determine EM energy and power deposition without the need to measure ambient field intensity values or overload-sensitive EMF survey equipment. Following measurement of relevant EM, thermal, and elastic material property values, a carbon-filled polytetrafluoroethylene (CF-PTFE) lossy dielectric medium subject to pulsed HPM was computationally modeled using the commercial finite element method multi-physics simulation software package COMSOL. The simulation was used to explore the impacts of various material properties on TA signal output as a function of simulated incident field power density, EM frequency, and pulse length, thereby informing the selection of system components for the further development of a full TA-based HPM detection chain.

Keywords: computer calculations; exposure; radiofrequency; microwaves; radiation; nonionizing

Health Phys. 122(6):673-684; 2022

AnActiveDoseMeasurementDeviceforUltra-short,Ultra-intenseLaserFacilities

Shuoyang Wei, Hui Gong, Honghu Song, Ankang Hu, Jun Xiong, Hui Zhang, Junli Li, Rui Qiu1

(1.Tsinghua University Department of Engineering Physics, Beijing, China)

Abstract:Ultra-short, ultra-intense laser facilities could produce ultra-intense pulsed radiation fields. Currently, only passive detectors are fit for dose measurement in this circumstance. Since the laser device could generate a dose up to tens of mSv outside the chamber in tens of picoseconds, resulting in a high instantaneous dose rate of ～107Sv s-1, it is necessary to perform real-time dose measurement to ensure the safety of nearby workers. Due to fast response and excellent radiation resistance, a diamond-based dose measurement device was designed and developed, and its dose-rate response and its feasibility for such occasions were characterized. The measurement results showed that the detector had a good dose-rate linearity in the range of 3.39 mGy h-1to 10.58 Gy h-1for an X ray source with energy of 39 keV to 208 keV. No saturation phenomenon was observed, and the experimental results were consistent with the results obtained from Monte Carlo simulation. The charge collection efficiency was about 80%. Experimental measurements and simulations with this dose measurement device were carried out based on the “SG-II” laser device. The experimental and simulation results preliminarily verified the feasibility of using the diamond detector to measure the dose generated by ultra-short, ultra-intense laser devices. The results provided valuable information for the follow-up real-time dose measurement work of ultra-short, ultra-intense laser devices.

Keywords: detector; radiation; lasers; Monte Carlo; radiation dose

Health Phys. 122(6):685-695; 2022

OvercomingtheFukushimaWastewaterCrisis:WhattheJapaneseAuthoritiesCouldDotoAddressOpposingViews

Kwan Hoong Ng1,2, David Yoong1, Jiankun Gong3

(1.Department of Biomedical Imaging, Faculty of Medicine, Universiti Malaya, Lembah Pantai, 50603 Kuala Lumpur, Malaysia;2. Department of Medical Imaging and Radiological Sciences, College of Health Sciences, Kaohsiung Medical University, 80708 Kaohsiung, Taiwan;3. Department of Media and Communication Studies, Faculty of Art and Social Science, Universiti Malaya, Lembah Pantai, 50603 Kuala Lumpur, Malaysia)

Abstract:In April 2021, the Japanese authorities’ announcement of their decision to release processed wastewater from the damaged Fukushima Daiichi nuclear power plant into the Pacific Ocean over 30 y, beginning in 2023, triggered strong domestic and international opposition. Failure to handle this situation tactfully can lead to public disorder, civil disobedience, loss of trust in the authorities, and even diplomatic sanctions. In this article, we explain the underlying reasons behind this resistance, and we offer some strategic methods that the Japanese authorities can deploy to address opposing views and overcome the Fukushima wastewater crisis.

Keywords: Fukushima Daiichi nuclear power plant; public information; waste disposal; risk communication

Health Phys. 122(6):696-704; 2022

ANSI3.1—2014andtheSupplementalWorkforceofRadiationProtectionTechnicians

Leldon Blue1

(1.BHI Energy, 2120 Johnson Marina Road, Chapin, SC 29036)

Abstract:Attrition in the supplemental workforce of radiation protection technicians continues to present challenges in supporting the US nuclear power industry with contract technicians during refueling outages, major projects, and decommissioning. Industry wide adoption of ANSI 3.1—2014,Selection,Qualification,andTrainingofPersonnelforNuclearPowerPlants, can help overcome these challenges by accelerating the training and development of technicians in the supplemental workforce by applying the systematic approach to training (SAT).

Keywords: operational topics; nuclear power industry; regulatory guides; safety standards

Health Phys. 122(6):726-731; 2022

ThyroidBioassayandDoseAssessmentSystemfor125IatWoodsHoleOceanographicInstitution

Ronald H. Reif, Dan Lopes1

(1.Environmental Health & Safety Department, Woods Hole Oceanographic Institution, Woods Hole, MA 02543)

Abstract:Woods Hole Oceanographic Institution (WHOI) conducts research involving125I. When an individual handles or works near unsealed radioiodine, including125I, above certain activities bioassays are required or may be required. Because of the quantities of125I being used for a research protocol, a thyroid bioassay and dose assessment system and procedure was developed to comply with this requirement. This procedure includes detector calibration, quality control, determination of recording level, determination of minimum detectable activity, thyroid bioassay (baseline, routine, special, and termination measurements), and intake and dose assessment calculations.

Keywords: operational topics;125I; dose assessment; thyroid

Health Phys. 122(6):732-736; 2022