Radiation protection issues on preparedness and response for a severe nuclear accident: experiences of the Fukushima accident

Radiation protection issues on preparedness and response for a severe nuclear accident are discussed in this paper based on the experiences following the accident at Fukushima Daiichi nuclear power plant. The criteria for use in nuclear emergencies in the Japanese emergency preparedness guide were based on the recommendations of International Commission of Radiological Protection (ICRP) Publications 60 and 63. Although the decision-making process for implementing protective actions relied heavily on computer-based predictive models prior to the accident, urgent protective actions, such as evacuation and sheltering, were implemented effectively based on the plant conditions. As there were no recommendations and criteria for long-term protective actions in the emergency preparedness guide, the recommendations of ICRP Publications 103, 109, and 111 were taken into consideration in determining the temporary relocation of inhabitants of heavily contaminated areas. These recommendations were very useful in deciding the emergency protective actions to take in the early stages of the Fukushima accident. However, some suggestions have been made for improving emergency preparedness and response in the early stages of a severe nuclear accident.

Influence of voxel size on specific absorbed fractions and S-values in a mouse voxel phantom

Photon and electron specific absorbed fractions (SAFs) and S-values have been evaluated using mouse voxel phantoms. In voxel phantoms, it is important to choose the voxel size carefully since it affects the accuracy of results. In this study, two mouse voxel phantoms were constructed, with cubic voxels, one with 0.1-mm sides and the other with 0.4-mm sides. The sources were considered to be distributed uniformly in the main organs and the radiation transport was simulated using the Monte Carlo code EGS4. It was found that the effect of voxel size on SAFs for self-irradiation was not high (<10 %) for electrons and photons. However, it was appreciable for cross-irradiation especially for electrons. The effect of voxel size was investigated on S-values for some beta emitters such as (131)I, (153)Sm, (188)Re and (90)Y.

Application of voxel phantoms and Monte Carlo method to whole-body counter calibration

Voxel phantoms and Monte Carlo methods are of considerable interest in calibrating in vivo counting applications for radioactive body burden such as whole-body counters. At the Japan Atomic Energy Research Institute (JAERI), a calculation code--UCWBC code--for whole-body counter calibrations using voxel phantoms has been developed as an EGS4 Monte Carlo user code. To validate the UCWBC code for calibrating whole-body counters at JAERI, response functions and counting efficiencies of a p-type high-purity Ge (HPGe) semiconductor detector used for the whole-body counter were evaluated for a water-filled block-shape phantom by use of UCWBC code and were measured by experiments. The voxel version of the water-filled block-shape phantom based on an actual phantom was used for the calculations. Furthermore, counting efficiencies of the Ge semiconductor detector for the male and female voxel phantoms developed at JAERI were evaluated in the photon energy range from 60 to 1836 keV by the UCWBC code in order to examine the differences between the counting efficiencies for voxel phantoms. In conclusion, it was found that the response functions and counting efficiencies of the Ge semiconductor detector found by the UCWBC code for the water-filled block-shape phantom are in good agreement with measured data. The UCWBC code was validated by those comparisons. It was also found that the counting efficiencies of the Ge semiconductor detector depend on the size of the phantoms and the effective distance between phantom and detector. The calibration of whole-body counters using voxel phantoms and Monte Carlo methods would be quite useful for the improvement in the accuracy of measurement results.

Evaluation of specific absorbed fractions in voxel phantoms using Monte Carlo simulation

There is a need to calculate specific absorbed fractions (SAFs) in voxel phantoms for internal dosimetry. For this purpose, an EGS4 user code for calculating SAFs using voxel phantoms was developed on the basis of an existing EGS4 user code for external dosimetry (UCPIXEL). In the developed code, the transport of photons, electrons and positrons in voxel phantoms can be simulated, particularly the transport simulations of secondary electrons in voxel phantoms. The evaluated SAFs for the GSF 'Child' voxel phantom using the developed code were found to be in good agreement with the GSF evaluated data. In addition, SAFs in adult voxel phantoms developed at JAERI were evaluated using the developed code and were compared with several published data. It was found that SAFs for organ self-absorption depend on the organ masses and would be affected by differences in the structure of the human body.

Application of a Ge semi-conductor detector to whole-body counter

To calibrate a whole-body counter, it is necessary to find a determination method for peak efficiencies of detectors used in the whole-body counter. For this purpose, peak efficiencies of a Ge semiconductor detector for point and volume sources were evaluated in the photon energy range 60-1836 keV by Monte Carlo simulation and experiment. It was found that the calculated peak efficiency curves as a function of energy without modelling of the actual sensitive region of the detector are similar in shape to those measured. The calculated peak efficiencies of the detector having an apparent dead layer (1 mm) were also found to agree with the experimental values (deviations from -10-24%). Consequently, the simulation method for peak efficiencies was validated. In addition, an optimum design for a whole-body counter with Ge semiconductor detectors was examined by simulation. This simulation provides a method to determine an optimum arrangement of detectors in a whole-body counter, offering a uniform response to various 137Cs distributions in a human body.

Uncertainties in estimated body burdens of caesium-137 by whole-body counting

It is very important to evaluate the uncertainties in individual monitoring for internal exposure of workers. The uncertainties in estimated body burdens of 137Cs with the JAERI whole-body counter were investigated using Monte Carlo simulation and measurements. It was found that the uncertainties of estimated body burdens with the whole-body counter are strongly dependent on various sources of uncertainty, such as radioactivity distribution within the body and counting statistics and that the 137Cs body burden assessed from the result of the whole-body count can be within +/- 60% in error.