Assessment of environmental public exposure from a hypothetical nuclear accident for Unit-1 Bushehr nuclear power plant
Unit-1 of the Bushehr nuclear power plant (BNPP-1) is a VVER-type reactor with 1,000-MWe power constructed near Bushehr city at the coast of the Persian Gulf, Iran. The reactor has been recently operational to near its full power. The radiological impact of nuclear power plant (NPP) accidents is of public concern, and the assessment of radiological consequences of any hypothetical nuclear accident on public exposure is vital. The hypothetical accident scenario considered in this paper is a design-basis accident, that is, a primary coolant leakage to the secondary circuit. This scenario was selected in order to compare and verify the results obtained in the present paper with those reported in the Final Safety Analysis Report (FSAR 2007) of the BNPP-1 and to develop a well-proven methodology that can be used to study other and more severe hypothetical accident scenarios for this reactor. In the present study, the version 2.01 of the PC COSYMA code was applied. In the early phase of the accidental releases, effective doses (from external and internal exposures) as well as individual and collective doses (due to the late phase of accidental releases) were evaluated. The surrounding area of the BNPP-1 within a radius of 80 km was subdivided into seven concentric rings and 16 sectors, and distribution of population and agricultural products was calculated for this grid. The results show that during the first year following the modeled hypothetical accident, the effective doses do not exceed the limit of 5 mSv, for the considered distances from the BNPP-1. The results obtained in this study are in good agreement with those in the FSAR-2007 report. The agreement obtained is in light of many inherent uncertainties and variables existing in the two modeling procedures applied and proves that the methodology applied here can also be used to model other severe hypothetical accident scenarios of the BNPP-1 such as a small and large break in the reactor coolant system as well as beyond design-basis accidents. Such scenarios are planned to be studied in the near future, for this reactor.
Public exposure from environmental release of radioactive material under normal operation of unit-1 Bushehr nuclear power plant
The Unit-1 Bushehr Nuclear Power Plant (BNPP-1), constructed at the Hallileh site near Bushehr located at the coast of the Persian Gulf, Iran, is a VVER type reactor with 1000 MWe power. According to standard practices, under normal operation conditions of the plant, radiological assessment of atmospheric and aquatic releases to the environment and assessment of public exposures are considered essential. In order to assess the individual and collective doses of the critical groups of population who receive the highest dose from radioactive discharges into the environment (atmosphere and aquatic) under normal operation conditions, this study was conducted. To assess the doses, the PC-CREAM 98 computer code developed by the Radiation Protection Division of the Health Protection Agency (HPA; formerly called NRPB) was applied. It uses a standard Gaussian plume dispersion model and comprises a suite of models and data for estimation of the radiological impact assessments of routine and continuous discharges from an NPP. The input data include a stack height of 100 m annual radionuclides release of gaseous effluents from the stack and liquid effluents that are released from heat removal system, meteorological data from the Bushehr local meteorological station, and the data for agricultural products. To assess doses from marine discharges, consumption of sea fish, crustacean and mollusca were considered. According to calculation by PC-CREAM 98 computer code, the highest individual dose in terrestrial area for adults is 14 × 10−5 mSv/y in ESE direction and 600 m distance from stack. Also, the individual dose via discharge of liquid effluents to the Persian Gulf is 5 × 10−7 mSv/y. Furthermore, total collective dose around BNPP-1 site within 100 km radial is calculated using local data and consumption habits. The results show that the radiological impact of the BNPP-1 on the critical groups of public and the individual effective doses are in good agreement with the values given in the Final Safety Analysis Report (FSAR-2007) and the Environmental Report of the BNPP-1. Also the calculated ambient gamma dose rates match relatively well with the monitored dose rate values of the environmental monitoring stations around the reactor under normal operation conditions. It can also be concluded that the estimated effective doses are lower than the dose constraint of 0.1 mSv/y associated with this plant. The results are presented and discussed.
An Optimization Approach to Occupant Safety and Fuel Economy in Vehicle Design
1. Abstract A major challenge in automotive design is the creation of safe vehicles with minimal environmental impact. This study presents a modeling framework for evaluating and optimizing body designs for improved occupant safety and fuel efficiency. Vehicle body mass is considered as the main link between safety and sustainability. The modeling framework includes frontal crash energy absorption, restraint system design and fuel economy. Preliminary results indicate a Pareto-optimal curve between safety and sustainability may exist when other factors are not taken into account. A more complete modeling framework that includes more sophisticated sustainability and safety metrics, cost and other market considerations, is suggested in order to support better design and regulatory decisions. 2. Keywords: Automotive body structures, fuel economy, occupant safety, optimal vehicle design, restraint systems