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One dimensional seismic response analysis on the ground surface of the Non-Commercial Power Reactor (RDNK) site based on the mean uniform hazard spectrum (UHS) and disaggregation analysis has been conducted. The study’s objective was to perform an analysis on site-specific response spectra on the ground surface based on existing mean UHS and disaggregation data of the site that correspond to a 1,000 and 10,000 year return period of earthquakes in compliance with the national nuclear regulatory body requirements of Indonesia. Detailed site characterization was defined based on secondary data of a geotechnical drill-hole, seismic cross-hole, downhole data, and microtremor array data. The dynamic site characteristic analysis was presented along with strong motion selection and processing using two types of strong motion datasets. An investigation of strong motion selection, spectral matching, and scaling has been presented as an essential step in ground motion processing. One-dimensional equivalent linear analysis simulation was performed by computing the processed ground motions. A seismic design spectrum and ground surface response spectra from the two datasets of strong motion, both corresponding to a 10,000 and 1,000 year return period, are presented at the end of this study. This study has shown that in order to establish the appropriate seismic response design spectrum, site-specific data and seismic hazard analysis must be immensely considered., Jednodimenzionalna seizmička analiza na tlu u okolici nekomercijalnoga nuklearnog reaktora temeljena je na izučavanju srednjih, uniformnih spektara rizika te analizi dezagregacije tla. Analiza je načinjena na smjestištu koje je određeno svojim posebnim seizmičkim spektrom. Spomenute varijable izučavane su s obzirom na povratno razdoblje potresa od 1000 i 10 000 godina te su uspoređene s nacionalnim zakonodavstvom o sigurnosti nuklearnih postrojenja u Indoneziji. Analizirano područje detaljno je opisano iz sekundarnih podataka koji su obuhvatili geotehničke i sezimičke bušotinske podatke te mjerenja mikropotresa. Dinamička svojstva smjestišta predstavljena su usporedno s podatcima iz dvaju skupova mjerenja snažnih gibanja. Njihovo izučavanje spektralnom analizom te odabirom mjerenja opisano je kao temeljni korak u izučavanju gibanja tla. Jednodimenzionalna analiza načinjena je računalnom obradbom. Prikazani su seizmički i površinski spektri, za oba skupa podataka i oba povratna razdoblja. Pokazano je kako ove metode trebaju nužno biti korištene u analizi seizmičkoga rizika na smjestištima ove vrste.

While inspecting the Natanz Nuclear Site (Iran) on October 6, 2019, an inspector of the IAEA was found to carry suspicious materials. She was prevented from entering the site by the Iranian authorities and was shortly returned to the Agency’s headquarters. Iran could not prosecute her, because of the inspector’s immunity by the Agency. However, in addition to exhaustion of the dispute settlement mechanisms predicted in the Agreement on the Privileges and Immunities of the IAEA which has also provided the recourse to the ICJ, Iran may prosecute the Agency by attributing the conduct of the inspector to the Agency in the national courts of non-member States of the Agency that has not accepted the immunity of international organizations as customary international law. This article deals with the immunity of international organizations and its agents, as well as examining the Agency inspector’s fault in inspecting the Natanz Nuclear Site and the Judicial Mechanisms for follow-ups.

1. Introduction During 2008 and 2010 the National Institute for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) organized two comprehensive field test campaigns (Wouters & Schiltz, 2013) situated in the NE of Flanders. The subject of these field campaigns was a hydrogeological safety study for a disposal facility for low radioactive waste storage. This investigation area is situated in the NE of the Flanders region in Belgium, at the Dessel nuclear site and a surrounding safety area on the territory of the Dessel–Geel–Kasterlee communities (Fig. 1). This field test campaign consisted in seven cored and logged boreholes and of about 200 CPTs (depth up to 35 m) in a regular grid of ~1 km² over an area of ~60 km² in the Dessel–Geel–Kasterlee area. This area is situated in a geological setting where, under a thin (1–4 m) cover of Quaternary sediments, Miocene sandy sediments outcrop (Fig. 1). In some preliminary minor field campaigns one of the cored boreholes revealed the presence of a ~10 m thick clayey layer on a stratigraphic level that was supposed to be sandy. Obviously the primary objective of the large number of CPTs was determining the presence and extension of this aquitard. It turned out that these data were also valuable in the discussion of the complex detail stratigraphy of the area. Therefore CPT data have been integrated in the unravelling of the local stratigraphy as presented in Vandenberghe et al. (2020, this volume). More information on the CP

This article assesses the radiological environment at the nuclear site of the Mayak PA, Russian Federation, during and after the accident in 1957, the so-called 'Kyshtym Accident', and the radiation doses to those who participated in the eradication of its consequences. Based on numerous archival documents, this paper presents the radiation data for 1957-1960, including individual dosimetry monitoring data and estimated doses to the Mayak workers, as well as the to personnel in supporting organisations and the military involved in the remediation operations. From 1957-1959 some 38 500 individuals took part in the clean-up actions and remediation of contaminated areas of the Mayak PA industrial site after the accident, including individuals exposed at the time of the accident: Mayak PA employees, militarypersonnel, and civil construction workers. External equivalent doses to 10 500 individuals were estimated in the range of 220 to 265 mSv, while there were cases of doses up to 950 mSv and higher. The collective dose received during the accident and its aftermath was in the region of 7300 person-Sv. By October-December 1957, the collective dose was about 4500 person-Sv. Collective doses recorded in 1958 and 1959 amounted to 2250 person-Sv and 480 person-Sv, respectively.

A method for the determination of 14C in air was validated with 4 N NaOH solution as absorbent medium. The chemical yield of the whole analytical process of precipitation of BaCO3 and re-absorption of released CO2 on acidification was determined by 14C spike experiments. A mean analytical recovery of 84.2% with a standard deviation of 7.21% was achieved. The propagated relative uncertainty of the method was 11.9%. The application of the method for routine monitoring around a nuclear facility was demonstrated through extensive air sampling in the vicinity of Tarapur Atomic Power Station, India. The 14C specific activity ranged between

A record of fluid flow has been documented within a Paleozoic carbonate platform sequence by U–Pb dating of calcite in veins and vugs from rock core sampled through a shallowly dipping sequence of sedimentary rocks beneath the Bruce nuclear site, Ontario, Canada. Secondary calcite from >650 m deep Ordovician carbonate rocks yields a Silurian age of 434 ± 5 Ma possibly related to infiltration of seawater from overlying evaporitic basins as well as hydrothermal solutions that infiltrated from below. In contrast, near-surface Devonian rocks mostly give vein infill ages over the range of 80–100 Ma with evidence for younger infill down to 50 Ma. Vein calcite samples previously dated from surface outcrops of Ordovician carbonate exposed up to 500 km to the east yielded similar U–Pb ages. Coincidence of near-surface vein calcite ages indicates widespread vein emplacement synchronous with a change in direction of motion of the North American plate as well as possible erosional unroofing following passage of the region over the Great Meteor hotspot approximately 125 Myr ago. Deeper carbonate formations have remained apparently impermeable to post-Paleozoic disturbance despite these perturbations.

Single cell gel electrophoresis (SCGE), also called comet assay, is a rapid and sensitive technique used to analyse DNA Fragmentation Index(DFI). This study aimed to evaluate DNA damage in lymphocytes due to ionizing radiation in workers of Al-Tuwaitha nuclear site, which has been used for nuclear activities and contains a potentially significant amount of radioactive waste.The workers in this site are vulnerable to pollution due to a highly polluted environment of ionizing radiation. Blood samples were collected from 36 workerswho were divided into two groups;8 workers without protection and 28workers with protection, in addition to 30 control subjects.Alkaline comet assay was applied for analysis and the results indicated significantly higher DNA damage in the workers without protection as compared with the workers with protection and control groups.The result also showed significant differences between the workers with protection and control groups.

French nuclear research began for military purposes and then further developed for business. This article traces the history of French nuclear development from the establishment of the French Atomic Energy Commission in 1945 to the present by dividing this period into six phases. Contrary to previous studies which focus on certain periods, seventy years of French nuclear history is investigated here. It describes the transition from military to civilian use, the development of the nuclear fuel cycle including the fast breeder reactor, spent nuclear fuel reprocessing, and disposal research. Additionally, based on a historical case study of the Marcoule site, the oldest nuclear site in France, this article shows that France will rely on back-end nuclear technology to survive in the twenty-first century.

The specific activity of 29 soil samples collected from FuelFabrication Facility FFF at AL-Tuwaitha site, 20 km south ofBaghdad were determined using HPGe detector in a low backgroundconfiguration, it's relative efficiency of 40%, and resolution of 2keVfor the 1332 keV gamma ray emission of 60Co. The range of activityconcentrations of 226Ra, 232Th and 40K were between (12.56-31.96),(10.2-18.4) and (47.47-402.1) Bq/kg respectively. In order to assessany radiological hazard to human health, the absorbed gamma doserate D in air at 1m above the ground surface was calculated in therange (18.87 to 36.46) nGy/h; the outdoor annual effective doseequivalent AEDE was evaluated to vary from 0.0039 to 0.0076mSv/y with the mean value 0.0059 mSv/y, this value comparable tothe worldwide effective dose 0.48mSv/y. The Radium EquivalentRaeq for all samples were evaluated and were lower than the acceptedsafety limit value of 370 Bq/kg. The results indicated that theradiation of hazards from primordial radionudlides in all samples inthis study is not significant.

Nuclear sites around the world are being decommissioned and remedial actions are being undertaken to enable the sites or parts of the sites to be reused. Although this is relatively straightforward for most sites, experience has suggested that preventative action is needed to minimise the impact of remediation activities on the environment and the potential burden to future generations. Removing all contamination in order to make a site suitable for any use generates waste and has associated environmental, social and economic detriments and benefits that should be taken into account. Recent experience of OECD Nuclear Energy Agency (NEA) member countries in the remediation of contaminated land, predominantly contaminated soil and groundwater, on nuclear sites during decommissioning has been assessed by an NEA task group. The experience was used to identify strategic considerations for nuclear site remediation, to consider the application of sustainability principles to nuclear site remediation, to describe good practice, and to make recommendations for further research and development. The key aspects that were identified were that 1) site remediation should be sustainable by resulting in an overall net benefit; and 2) an adaptive approach is essential in order to take into account the inherent uncertainty associated with the decommissioning and site remediation timescales. A report describing the findings was published by OECD/NEA in 2016. The conclusions provide insights to decision makers, regulators, implementers and stakeholders involved in nuclear site decommissioning so that they can achieve sustainable remediation of nuclear sites, now and in the future.

The potential consequences for Norway should a nuclear accident at the Sellafield nuclear site occur, have been of concern for Norwegian authorities for several decades. Meteorological data from a 33-year period and the dispersion model ‘SNAP’ were used to evaluate meteorological conditions for which atmospheric transport of radionuclides from Sellafield to Norway would lead to the most severe impacts. The worst-case meteorological scenario for Norway, was found on 25th June 1989 for a low elevation (0–800 m) release and on 29th June 2001 for a higher elevation (800–1600 m) release. In both cases the western part of Norway was most affected. In general, the probability for depositions (>10 Bq/m2 of 137Cs) increased about 40% during the autumn and winter compared to the spring and summer months. An influence of climate change on the depositions was analysed, but not verified. Results from a number of simulations were also compared to identify how factors such as radioactive particle characteristics and initial release conditions could affect the predicted radionuclide deposition. The impact on predicted total depositions as well as hot-spot depositions by varying particle density and size as well as release elevation in worst-case scenario simulations amounted to about 40%–50%.

Temporal data mining (TDM) is an active and rapidly evolving area in big data science. Is it possible to borrow the concepts and algorithms of TDM and apply them to nuclear site monitoring and in situ decommissioning (ISD) research? Since all the data collected from the nuclear-decommissioning sites are time-specific, age-specific, and development stage–specific, they are ideal for TDM analysis to validate system performance and reveal unknown patterns of material failure, liquid leaking, and radiation field changing. Savannah River National Laboratory has established an ISD Sensor Network Test Bed—a unique, small-scale, and configurable environment—for the assessment of prospective sensors on actual ISD system at minimal cost. This chapter analyzed the baseline data collected by ISD test bed in recent years with the assistant of TDM algorithms/codes to find out frequency episodes in the event stream. The results have confirmed that TDM techniques and corresponding codes are effective tools to validate ISD performance, and the frequent episodes found in the data stream not only showed the daily cycle of the sensor responses but also established the response sequences of different types of sensors, which was verified by the actual experimental setup. Some abnormal patterns may have the potential for prediction of system failures.

In situ measurements are made without the removal of a physical sample and have many advantages over traditional ex situ measurements, made on a removed sample usually in a remote laboratory. The quality of ex situ measurements is usually expressed primarily in terms of their measurement uncertainty, including that arising during the sampling process. However, estimates of uncertainty for in situ measurement values have not usually included this uncertainty from sampling (UfS). It is argued that the making of an in situ measurement inevitably includes the taking of an ‘undisturbed sample’ that generates UfS, which should be included in the estimate of measurement uncertainty. Because undisturbed samples are not prepared or mixed, as is usual for removed samples, the heterogeneity of the analyte concentration in the sampling target is the primary source of UfS. Existing methods for estimating UfS for ex situ measurements can broadly be applied to in situ measurements. However, four extra challenges that limit the design and uptake of uncertainty estimation for in situ methods are identified, and possible solutions and actions required are discussed. Examples of in situ measurements considered include Pb in top soil by hand-held PXRF, 137Cs at a nuclear site by portable gamma-ray spectrometry, and bilirubin in new-born infants by hand-held reflectance photometry.

No commercially available detector system can measure alpha, beta and gamma-rays at the same time and separately with good efficiency, while being cost-effective, portable and offering real-time monitoring. The main purpose of an alpha-beta-gamma detector would be for safety management and nuclear decommissioning in the nuclear industry. This idea for a detector system became more valuable, after Fukushima in Japan, because nuclear waste can contain fission products and transactinide materials which not only emit gamma-rays but also emit alpha and beta particles and in some cases, neutrons. In this research, we investigated the best available alpha-beta-gamma radiation detector materials and their optimum thickness by using Geant4 based GATE simulation. The work revealed a better efficiency result for each radiation type than in previous work. In the simulation, 0.05 mm ZnS(Ag), 3.2 mm plastic scintillator and 1.75 mm BGO were found to be best for the detection and identification of alpha, beta and gamma-rays respectively. In nuclear medicine, this type of detector system could also modify to become a miniaturized radio-guided surgery beta-gamma probe beside of the modification into the robotic surgery. This research result will influence three different areas in imaging technology, homeland security and nuclear industry.

In the present study the radon concentration was measured in indoor places by the RAD7 (radon detector) was in some locations at Al-Tuwaitha nuclear site and some surrounding areas for the duration from 13/10/2016 to 2/1/2017 and the measurement of the indoor radon concentration ranged from (4.96±4.4 to 102±25) Bq/m3. The high value of radon has been found at decommissioning directorate /emergency room, which is lower than the action value recommended by the Environmental Protection Agency (EPA) which is (148 Bq/m3) while the lowest value has been founded in central laboratories directorate \ models room. These values were used to calculate the annual effective dose and the health risks for cells bronchial which caused by the inhalation of radon. The values of the annual effective doses were calculated and ranged from (0.1249 to 2.5704) mSv/y these results are lower than the value of (10 mSv/y) recommended by the International Commission Radiological on Protection (ICRP). The results from this study shows that the region has background radioactivity levels within the natural limits.

RESRAD is a computer model designed to estimate risks and radiation doses from residual radioactive materials in soil. Thirty seven soil samples were collected from the area around the berms of Al-Tuwaitha site and two samples as background taken from an area about 3 km north of the site. The samples were measured by gamma-ray spectrometry system using high purity germanium (HPGe) detector. The results of samples measurements showed that three contaminated area with 238U and 235U found in the study area. Two scenarios were applied for each contaminated area to estimate the dose using RESRAD (onsite) version 7.0 code. The total dose of resident farmer scenario for area A, B and C are 0.854, 0.033 and 2.15×10-3 mSv.yr-1, respectively. While suburban resident scenario for area A, B and C are 0.807, 0.031 and 2.04×10-3 mSv.yr-1, respectively.

In the management of radionuclide release in the environment, the unsaturated zone could be a natural barrier to delay or to stop the radionuclide migration through the environment and to protect the groundwater from radiological risks. Thus, a suitable scientific evaluation of any radionuclide transport problems related to groundwater may to take into account the processes affecting flow through the unsaturated zone. In this work, an approach that involves the interactions between unsaturated zone and saturated zone both from hydrogeological and radionuclide transport point of view is proposed. This approach was tested developing a case study on an Italian nuclear site. The behavior of unsaturated zone as protective barrier for the groundwater was highlighted and identified as a fundamental aspect in the development of environmental analysis concerning the radionuclide transport into the environment. Promising results were found to improve the design of a radiological monitoring network.

The potential for adverse health effects from internal exposure to Plutonium has been recognised since its discovery in the 1940s. However, in the absence of specific information, potential risks from Plutonium exposure have always largely been controlled through knowledge of radiation exposure risks in general, much of which comes from external radiation exposures. To try to obtain more direct estimates of potential internal exposure risks, epidemiological studies of Plutonium workers need to be conducted. Such epidemiological analyses require individual Plutonium exposure estimates that are as accurate and unbiased as possible. The UK Sellafield workforce includes one of the world’s largest cohorts of Plutonium workers, which constitutes, by some considerable margin, the group of workers most comprehensively monitored for internal exposure to this alpha-particle-emitter. However, for several hundred workers employed at the start of Plutonium work at the facility, during the period from 1952 through to 1963, the historical urinalysis results available cannot provide sufficiently accurate and unbiased exposure assessments needed for use in epidemiological studies. Consequently, these early workers have had to be excluded from epidemiological analyses and this has significantly reduced the power of these studies. A promising quantitative methodology to overcome the issue of missing or deficient exposure data, is to use exposure data from other sources to estimate the average exposure a ‘typical worker’ would have received, and to collate this information for specific occupations and years. This approach is called a Job-Exposure Matrix (JEM). Work on a pilot study to construct a population-specific quantitative JEM for the early Plutonium workers at Sellafield during 1952–1963, for whom reliable urinalysis results do not exist, has shown the potential for a JEM approach to produce more reliable and useful exposure estimates for epidemiological research.

Background: The emergency planning zone (EPZ) of the city of Busan is divided into the precautionary actions zone (PAZ) and the urgent protective action planning zone; which have a 5-km radius and a 20-km to 21-km radius from the nuclear power plant site, respectively. In this study, we assumed that a severe accident occurred at Shin-Kori nuclear unit 3 and evaluated the dispersion speed of radiological material at each distance at various wind speeds, and estimated the effective dose equivalent and the evacuation time of PAZ residents with the goal of supporting off-site emergency action planning for the nuclear site. Materials and Methods: The total effective dose equivalent, which shows the effect of released radioactive materials on the residents, was evaluated using the RASCAL 4.2 program. In addition, a survey of 1,036 residents was performed using a standardized questionnaire, and the resident evacuation time according to road and distance was analyzed using the VISSIM 6.0 program. Results and Discussion: According to the results obtained using the VISSIM and RASCAL programs, it would take approximately 80 to 252.2 minutes for permanent residents to move out of the PAZ boundary, 40 to 197.2 minutes for students, 60 to 232.2 minutes for the infirm, such as elderly people and those in a nursing home or hospital, and 30 to 182.2 minutes for those temporarily within the area. Consequently, in the event of any delay in the evacuation, it is estimated that the residents would be exposed to up to 10 mSv·h-1 of radiation at the Exclusion Area Boundaries (EAB) boundary and 4-6 mSv·h-1 at the PAZ boundary. Conclusion: It was shown that the evacuation time for the residents is adequate in light of the time lapse from the initial moment of a severe accident to the radiation release. However, in order to minimize the evacuation time, it is necessary to maintain a system of close collaboration to avoid traffc congestion and spontaneous evacuation attempts.

The safe and cost-effective decommissioning of legacy nuclear sites relies on accurate measurement of the radioactivity content of the waste materials, so that the waste can be assigned to the most appropriate disposal route. Such measurements are a new challenge for the science of radionuclide metrology which was established largely to support routine measurements on operating nuclear sites and other applications such as nuclear medicine. In this paper, we provide a brief summary of the international measurement system that is established to enable nuclear site operators to demonstrate that measurements are accurate, independent and fit for purpose, and highlight some of the projects that are underway to adapt the measurement system to meet the changing demands from the industry.

The role of soil-structure interaction (SSI) on the risk of unacceptable performance of five non-structural components of a nuclear reactor is investigated through a representative case study consisting of a pressurized-water reactor sited at Holyhead, United Kingdom. The seismic hazard at the site is defined by a 10,000 years uniform hazard spectrum, and its corresponding design response spectrum computed for a target structural performance goal of 1 × 10−5. Nine hypothetical soil profiles, with shear wave velocities ranging from 300 m/s to 1,200 m/s, are considered. Non-linear site response analyses are performed to determine the input motion at the foundation level; seismic capacity and demand of the components are computed using response-history analyses. To obtain high-confidence performance estimates from a limited number of results, Monte-Carlo simulation is used to expand the seismic demand matrix. It is shown that the probability of unacceptable performance of the reactor is highly sensitive to SSI effects. Specifically, the beneficial effects induced by SSI on the seismic performance of the reactor are limited to models sited on stiffer soil deposits (ie, Vs ≥ 900 m/s), whereas, the median probability of unacceptable performance increases for medium-to-soft deposits.

Consequences for Norway in case of a hypothetical accident in Sellafield nuclear site have been of concern for Norwegian authorities for some time now. A 33-year period with meteorological data and the dispersion model SNAP was used to find out the meteorological conditions for which atmospheric transport of radioactive debris from Sellafield nuclear site to Norway is the most efficient. This was done by running the SNAP model two times each day for the entire period and selecting the situations with maximum deposition to Norwegian territory. The worst case meteorological scenario for Norway in case of a hypothetical accident in Sellafield was found on 25th of June 1989. In this meteorological situation atmospheric transport to the west coast of Norway takes only 12 h. Based on the results of the SNAP runs, the probability of reaching Norway by radioactive pollution in case of an accident in Sellafield was also analysed. Such a probability is high (25–40%) for most of the Norwegian territory, except for the northern part and very high (over 40%) for the western coast of Norway.

The present study investigates whether there is an excess incidence of thyroid cancer among people living in the vicinity of the nuclear sites in Belgium. Adjusted Rate Ratios were obtained from Poisson regressions for proximity areas of varying sizes. In addition, focused hypothesis tests and generalized additive models were performed to test the hypothesis of a gradient in thyroid cancer incidence with increasing levels of surrogate exposures. Residential proximity to the nuclear site, prevailing dominant winds frequency from the site, and simulated radioactive discharges were used as surrogate exposures. No excess incidence of thyroid cancer was observed around the nuclear power plants of Doel or Tihange. In contrast, increases in thyroid cancer incidence were found around the nuclear sites of Mol-Dessel and Fleurus; risk ratios were borderline not significant. For Mol-Dessel, there was evidence for a gradient in thyroid cancer incidence with increased proximity, prevailing winds, and simulated radioactive discharges. For Fleurus, a gradient was observed with increasing prevailing winds and, to a lesser extent, with increasing simulated radioactive discharges. This study strengthens earlier findings and suggests increased incidences in thyroid cancer around two of the four Belgian nuclear sites. Further analyses will be performed at a more detailed geographical level. This study is carried out in the framework of the tasks of the Scientific Institute of Public Health (WIV-ISP). As a scientific institute, costs for open access publications are foreseen in the WIV-ISP policy.

In the fall of 1996, I traveled to the Chernobyl nuclear site in Ukraine with Dr. Clare Moisey, a Canadian doctor who was associated with a nonprofit organization called the Chernobyl’s Children Project. After the unnerving, unofficial visit to the Pripyat village site, which was a ghost town by then, Moisey decided to detour to the outlying areas of the so-called exclusion zone, where hundreds of mostly elderly people were beginning to illegally resettle. They had gotten tired of living in the drab, concrete apartment towers they were relocated to in Kiev following the disaster. “I would rather die of radiation poisoning than spend my last year rotting in that place,” said one widower we visited. We heard the same from others.

Due to often intense levels of radiation, many of the nuclear industry’s mechanical handling operations are conducted inside heavily shielded concrete structures, known as caves (UK) or canyons (USA). This chapter describes the equipment that is deployed in and around these inaccessible environments, from shielding windows, which allow operators to safely view the scene, to manipulators that can mimic an operator’s hand movements. It covers the decontamination processes which are employed to remove radioactive materials, and the substantial shield doors which segregate highly radioactive environments from adjacent areas which may be occupied by maintenance personnel. In addition, the chapter describes the various types of heavily shielded steel flasks that are used to carry radioactive materials across nuclear sites and also the highly robust types which are employed to transport materials in the public domain beyond a nuclear site’s boundaries.

A nuclear facility is arguably the most difficult industrial facility to site, especially with regard to public acceptance. Public resistance to such facilities is a complex blend of emotion-laden imagery coupled with a risk perception process that is diametrically opposed to the scientific process by which scientists define nuclear risks. While much of the literature that deals with risk perception and public acceptance considers the problem (and any offered solutions) for a single societal standpoint, the issue becomes more complex when the community is made up of many different cultures—especially when the set of cultures includes aboriginal people (“Aboriginal,” for the purposes of this paper, is meant to represent all First People, regardless of what they or their governments call them, including Native Americans and Eskimos (US), First Nations and Aboriginal People (Canada), the Maoris of New Zealand, the Aborigines of the Australian Outback and any other culture that predates Western discovery. No disrespect is intended by this simplification.) for whom there is a traditional and spiritual relationship with the land. The level of success that owners have when attempting to site a nuclear facility appears to be correlated with the homogeneity of the host community population. This paper offers insights for successful public outreach and acceptance when dealing with more diverse local cultures, based on lessons learned, in part, from the efforts of Ontario Power Generation’s permit to construct and operate a Deep Geologic Repository (DGR) for low- and intermediate-level waste at the Bruce Nuclear Site in the Municipality of Kincardine, Ontario, Canada.

International audience; The Fukushima Dai-ichi nuclear accident led to massive atmospheric deposition of radioactive substances onto the land surfaces. The spatial distribution of deposits has been estimated by Japanese authorities for gamma-emitting radionuclides through either airborne monitoring surveys (since April 2011) or in situ gamma-ray spectrometry of bare soil areas (since summer 2011). We demonstrate that significant differences exist between the two surveys for radiocaesium isotopes and that these differences can be related to dry deposits through the use of physically based relationships involving aerosol deposition velocities. The methodology, which has been applied to cesium-134 and cesium-137 deposits within 80-km of the nuclear site, provides reasonable spatial estimations of dry and wet deposits that are discussed and compared to atmospheric numerical simulations from the Japanese Atomic Energy Agency and the French Institute of Radioprotection and Nuclear Safety. As a complementary approach to numerical simulations, this field-based analysis has the possibility to contribute information that can be applied to the understanding and assessment of dose impacts to human populations and the environment around Fukushima. © 2014 American Chemical Society.

This study identified the terrain and building effects on the atmospheric dispersion of radioactive materials at the Wolsong Nuclear Site. To analyze the atmospheric dispersion of radioactive materials, the AERMOD-PRIME model, CFD model and meteorological data from 2010 were used. The terrain and building effects on the atmospheric dispersion of radioactive materials within a 1 km radius of the site were statistically significant. The maximum concentration of the radioactive material increased by 7 times compared to the concentration when the terrain and building effects were not considered. It was found that the terrain and building influenced the decrease in the concentration of radioactive material in a concentric circle with a 914 m radius from the center of the site. The concentration of radioactive material in a concentric circle with a 350 m radius was two-times higher than the concentration estimated at the backside of the building, which is the downwind side, without any consideration of the terrain and building effects. In consideration of the Korean situation, in which multiple nuclear reactors are built on the same nuclear site, it is necessary to evaluate the risk that may affect workers and nearby residents by reflecting the terrain and building effects.

Knowledge brought by survey data review from CEA Valduc about transfers in the different environmental compartments. The objective of this document is to describe the behavior of tritium in the environmentfromthesitesurvey dataofaFrench researchcenter.Sincethelate60s, the nuclear site of Valduc has discharged tritium gas and tritiated water into the atmosphere. Those discharges have led to a transfer to the nearby groundwater and rivers. An assessment of the tritium migrating through the hydrogeological system during the 1969-2009 period is presented. Surface survey data also provide a lot of information about transfers by the air pathway to the different compartments: air, rain, soil, plants and animals. The ratios between the different compartment concentrations show that air-leaf transfer is significant, that rain and air deposition are of the same order of magnitude, and that a relatively good equilibrium exists between the free and organic material water of plants. Some outdoor experiments confirm, in agreement with the literature, the level of incorporation in organic materials. Outside the center, water always remained below the present WHO limit

Safety and transient analyses of a pressurised water reactor (PWR) using the Personal Computer Transient Analyzer (PCTRAN) simulator was carried out. The analyses presented a synergistic integration of a numerical model; a full scope high fidelity simulation system which adopted point reactor neutron kinetics model and movable boundary two phase fluid models to simplify the calculation of the program, so it could achieve real-time simulation on a personal computer. Various scenarios of transients and accidents likely to occur at any nuclear power plant were simulated. The simulations investigated the change of signals and parameters vis a vis loss of coolant accident, scram, turbine trip, inadvertent control rod insertion and withdrawal, containment failure, fuel handling accident in auxiliary building and containment, moderator dilution as well as a combination of these parameters. Furthermore, statistical analyses of the PCTRAN results were carried out. PCTRAN results for the loss of coolant accident (LOCA) caused a rapid drop in coolant pressure at the rate of 21.8KN/m2/sec triggering a shutdown of the reactor protection system (RPS), while the turbine trip accident showed a rapid drop in total plant power at the rate of 14.3 MWe/sec causing a downtime in the plant. Fuel handling accidents mimic results showed release of radioactive materials in unacceptable doses. This work shows the potential classes of nuclear accidents likely to occur during operation in proposed reactor sites. The simulations are very appropriate in the light of Nigeria’s plan to generate nuclear energy in the region of 1000 MWe from reactors by 2017.