DOSIMETRY AND CANCER RISK ESTIMATIONS FOR DIFFERENT RADIATION PROTECTION SOLUTIONS AT DECOMMISSIONING A CONTAMINATED NUCLEAR POWER PLANT SITE.

Contaminated sediments originating from dredging activities in a nuclear power plant site were placed in a pond, which has to be taken into consideration during the future decommissioning process. The sediments have to be handled to free release the site. The radionuclides Co-60 and Cs-137 were identified and the activity concentrations (Bq/kg) were quantified in the range of 10-6000 and 5-50 Bq kg-1, respectively. The absorbed dose rate to individuals of various ages and sex present at the site of the dry pond area was estimated. The radiological impact in terms of lifetime attributable risk (LAR) and effective dose were calculated. For a 30-year-old male exposed during one year without any action regarding the sediments in the dried out pond, the LAR was predicted to be 0.0027, which recalculated to effective dose corresponds to 7.6 mSv year-1. The calculations show that countermeasures will be needed for the contaminated site.

IDACstar: A MCNP Application to Perform Realistic Dose Estimations from Internal or External Contamination of Radiopharmaceuticals.

A Monte Carlo-based stand-alone program, IDACstar (Internal Dose Assessment by Computer), was developed, dedicated to perform radiation dose calculations using complex voxel simulations. To test the program, two irradiation situations were simulated, one hypothetical contamination case with 600 MBq of 99mTc and one extravasation case involving 370 MBq of 18F-FDG. The effective dose was estimated to be 0.042 mSv for the contamination case and 4.5 mSv for the extravasation case. IDACstar has demonstrated that dosimetry results from contamination or extravasation cases can be acquired with great ease. An effective tool for radiation protection applications is provided with IDACstar allowing physicists at nuclear medicine departments to easily quantify the radiation risk of stochastic effects when a radiation accident has occurred.

SILICON DIODE AS AN ALPHA PARTICLE DETECTOR AND SPECTROMETER FOR DIRECT FIELD MEASUREMENTS.

A windowless silicon (Si) diode (4 mm(2)) was evaluated as alpha particle detector and spectrometer for field measurements. It was irradiated with alpha particles from a (241)Am (2.3 kBq) and a (210)Po (9 kBq) source at source-detector distances (SDD) of 0.5, 1.0 and 1.8 cm. The energy resolution in terms of full width at half maximum was 281, 148 and 113 keV for SDD of 0.5, 1.0 and 1.8 cm, respectively. The minimum detectable activity increased from 0.08 to 0.83 Bq when the SDD increased from 0.5 to 1.8 cm. The detector has the potential for several alpha spectrometric applications, such as monitoring for wound, skin and surface contamination at nuclear fuel facilities, nuclear power plants and facilities handling radioactive waste. Other areas are environmental surveys following releases of actinides at accidents in nuclear power plants and in connection with other radiological or nuclear scenarios.

A PHANTOM FOR DETERMINATION OF CALIBRATION COEFFICIENTS AND MINIMUM DETECTABLE ACTIVITIES USING A DUAL-HEAD GAMMA CAMERA FOR INTERNAL CONTAMINATION MONITORING FOLLOWING RADIATION EMERGENCY SITUATIONS.

The purpose of this study was to derive calibration coefficients (in terms of cps kBq(-1)) and minimum detectable activities, MDA, (in terms of kBq and corresponding dose rate) for the dual head gamma camera part of an SPECT/CT-instrument when used for in vivo internal contamination measurements in radiation emergency situations. A cylindrical-conical PMMA phantom with diameters in the range of 7-30 cm was developed in order to simulate different body parts and individuals of different sizes. A series of planar gamma camera investigations were conducted using an SPECT/CT modality with the collimators removed for (131)I and (137)Cs, radionuclides potentially associated with radiation emergencies. Energy windows of 337-391 and 490-690 keV were selected for (131)I and (137)Cs, respectively. The measurements show that the calibration coefficients for (137)Cs range from 10 to 19 cps kBq(-1) with MDA values in the range of 0.29-0.55 kBq for phantom diameters of 10-30 cm. The corresponding values for (131)I are 12-37 cps kBq(-1) with MDA values of 0.08-0.26 kBq. An internal dosimetry computer program was used for the estimation of minimum detectable dose rates. A thyroid uptake of 0.1 kBq (131)I (representing MDA) corresponds to an effective dose rate of 0.6 µSv d(-1) A (137)Cs source position representing the colon with an MDA of 0.55 kBq corresponds to an effective dose rate was 1 µSv y(-1) This method using a simple phantom for the determination of calibration coefficients, and MDA levels can be implemented within the emergency preparedness plans in hospitals with nuclear medicine departments. The derived data will help to quickly estimate the internal contamination of humans following radiation emergencies.

CAN AN ENERGY-COMPENSATED SOLID-STATE X-RAY DETECTOR BE USED FOR RADIATION PROTECTION APPLICATIONS AT HIGHER PHOTON ENERGIES?

The objective of this study was to investigate the characteristics of a solid-state detector commonly available at hospitals for parallel use as a real-time personal radiation monitor following radiation emergency situations. A solid-state detector probe with an inherent filtration (R100, RTI Electronics AB, Mölndal, Sweden) was chosen for evaluation. The energy dependence and the linearity in signal response with kerma in air were examined, and the detector was exposed to both X-ray beams using a conventional X-ray unit with effective photon energies ranging between 28.5 and 48.9 keV and to gamma rays 1.17 and 1.33 MeV from (60)Co. The R100 exhibited ∼1.7 times over-response at the lowest X-ray energy relative to the (60)Co source. The detector demonstrated a linear response (R(2) = 1) when irradiated with (60)Co to air kerma values in the range of 20-200 mGy. The conclusion is that high-energy photons such as those from (60)Co can be detected by the R100 with an energy response within a factor of <2 over the energy range examined and that the detector can provide real-time dose measurements following nuclear or radiological events.

Gafchromic film as a fast visual indicator of radiation exposure of first responders.

Three types of Gafchromic films have been studied to investigate their potential for use as a visually readable dosemeter for persons acting as first responders in connection with radiological or nuclear emergencies. The two most sensitive film types show a pronounced variation in sensitivity by photon energy and are therefore not suitable for use in cases of unknown exposures. The third film type tested (RTQA2), which is intended for quality control in radiation therapy has a sensitivity that is independent of the radiation quality, and is therefore considered as the most optimal for visual reading in situ. Tests carried out on a group of 10 human observers showed that absorbed doses down to 40 mGy can be detected by the eye. Read by a portable densitometer, qualitative absorbed dose estimates down to 9 mGy can be achieved. The colour change is obtained instantaneously, giving first responders immediate information about the presence of beta-, gamma- and X-ray radiation.