Verification of screening level for decontamination implemented after Fukushima nuclear accident

The 2021 Bo Lindell Lecture: Inclusive, accountable, transparent: the direction we should take for the benefit of present and future generations

The International Commission on Radiological Protection (ICRP) is recognised as the de-facto world authority in the field of radiological protection. The ICRP Recommendations have been used as a basis for regulations and policy in almost every country, and with the current review and revision of the System of Radiological Protection, it will continue to make significant contributions in radiation safety for patients, workers, the public, and the environment. In a society undergoing significant change, it is necessary to give careful thought to which groups will be perceived as authoritative organisations by the constituents of the future. The ideal form of an authoritative organisation in the new society of the future is to continue to show how it came to make such recommendations, how it reflected the opinions of interested parties in the process, and how it discloses its records with as much transparency as possible. The question now is what we must do to ensure that decision-making advances in a way that not only makes sense to the present generation, but will be easily consumed by future generations. The path that ICRP is taking to formulate the next set of General Recommendations is doing just that, in line with the key procedural values of INCLUSIVE, ACCOUNTABLE, AND TRANSPARENT.

Public health response and medical management of internal contamination in past radiological or nuclear incidents: A narrative review

Following a radiological or nuclear emergency, workers, responders and the public may be internally contaminated with radionuclides. Screening, monitoring and assessing any internal contamination and providing necessary medical treatment, especially when a large number of individuals are involved, is challenging. Experience gained and lessons learned from the management of previous incidents would help to identify gaps in knowledge and capabilities on preparedness for and response to radiation emergencies. In this paper, eight large-scale and five workplace radiological and nuclear incidents are reviewed cross 14 technical areas, under the broader topics of emergency preparedness, emergency response and recovery processes. The review findings suggest that 1) new strategies, algorithms and technologies are explored for rapid screening of large populations; 2) exposure assessment and dose estimation in emergency response and dose reconstruction in recovery process are supported by complementary sources of information, including 'citizen science'; 3) surge capacity for monitoring and dose assessment is coordinated through national and international laboratory networks; 4) evidence-based guidelines for medical management and follow-up of internal contamination are urgently needed; 5) mechanisms for international and regional access to medical countermeasures are investigated and implemented; 6) long-term health and medical follow up programs are designed and justified; and 7) capabilities and capacity developed for emergency response are sustained through adequate resource allocation, routine non-emergency use of technical skills in regular exercises, training, and continuous improvement.

Lessons from past radiation accidents: Critical review of methods addressed to individual dose assessment of potentially exposed people and integration with medical assessment

The experiences of the Chernobyl and Fukushima nuclear accidents showed that dosimetry was the essential tool in the emergency situation for decision making processes, such as evacuation and application of protective measures. However, at the consequent post-accidental phases, it was crucial also for medical health surveillance and in further adaptation to changed conditions with regards to radiation protection of the affected populations. This review provides an analysis of the experiences related to the role of dosimetry (dose measurements, assessment and reconstruction) regarding health preventive measures in the post-accidental periods on the examples of the major past nuclear accidents such as Chernobyl and Fukushima. Recommendations derived from the review are called to improve individual dose assessment in case of a radiological accident/incident and should be considered in advance as guidelines to follow for having better information. They are given as conclusions.

Estimated Thyroid Inhalation Doses Based on Body Surface Contamination Levels of Evacuees After the Fukushima Daiichi Nuclear Power Plant Accident

Doses of inhaled radionuclides received during evacuation might be correlated with amounts of those radionuclides on an evacuee's body surface. The purpose of the present study was to estimate thyroid equivalent doses based on body surface contamination measured with a Geiger-Mueller survey meter on 2,087 evacuees from Tomioka, Okuma, Futaba, Naraha, Namie, Minamisoma, and other municipalities in Japan. The measurement value in cpm was translated into Bq cm according to the radionuclide composition obtained by germanium gamma-spectrometry analyses of two persons' clothing. Thyroid equivalent dose by inhalation was estimated by two-dimensional Monte Carlo simulation based on the distribution of body surface radionuclide concentration and a uniform distribution of deposition velocity. For evacuees exposed twice on 12 and 15 March, the mean, median, and 90th percentile of inhalation thyroid equivalent dose for 1-y-old children were 21.4 mSv, 4.7 mSv, and 40.1 mSv for the Namie group; 7.3 mSv, 5.1 mSv, and 14.8 mSv for the Minamisoma group; and 2.3 mSv, 0.5 mSv, and 4.0 mSv for the group comprising Tomioka, Okuma, Futaba, and Naraha. These estimates are smaller than estimates in the United Nations Scientific Committee on the Effects of Atomic Radiation 2013 report but closer to estimates based on direct thyroid I measurement or indirect estimates based on Cs measurements made with a whole-body counter under the assumption that the ratio of I to Cs is 3.8.

Body Surface Contamination Levels of Residents under Different Evacuation Scenarios after the Fukushima Daiichi Nuclear Power Plant Accident

Body surface contamination levels should be correlated with inhaled actual thyroid doses during evacuation following the Fukushima Daiichi nuclear power plant (FDNPP) accident. Evacuees and residents were screened for body surface contamination using a Geiger-Mueller survey meter. The authors obtained 7,539 individual screening data sheets as well as gamma-spectrometry data from measurements made on clothing of two subjects by using a germanium spectrometer. Body surface contamination levels were analyzed in four residential groups during two different periods: 12-14 and 15-17 March 2011. Contamination levels during 12-14 March in the Tomioka/Okuma/Futaba/Naraha group were very low, indicating that residents evacuated before the radioactive plume reached their towns on 12 March. In contrast, levels in the Namie and Minamisoma groups were higher than those in the other groups in both periods, indicating that these residents were exposed to plumes twice on 12 and 15-16 March. The plume on 12 March was enriched with short-lived radionuclides: averaged proportions of radioactivity (relative to I) from Te, I, and Cs measured in clothing from two subjects were 2.3, 1.1, and 0.1, respectively, after correction for physical decay by 12:00 on 12 March. These proportions are similar to those (relative to I) from Te and Cs in dust sampled by a high-volume air sampler in the zone 20 km from the FDNPP on 12 March: 1.9 and 0.1, respectively. These data indicate that the relative contribution to inhaled thyroid dose of short-lived radionuclides in radioactive plumes released on 12 March could be as much as 37.5% in 1-y-old children.

Operational level for unconditional release of contaminated property from affected areas around Fukushima Daiichi nuclear power plant

This paper focuses on the surface contamination control of slightly contaminated property after the Fukushima nuclear accident. The operational level for the unconditional release of contaminated properties is calculated in counts per minute (cpm) to enable the use of a typical Geiger-Muller (GM) survey meter with a 50-mm bore, on the basis of the surficial clearance level of 10 Bq cm(-2) for (134)Cs and (137)Cs derived in the previous studies of the authors. By applying a factor for the conversion of the unit surface contamination to the count rate of a survey meter widely used after the Fukushima accident, the operational level for the unconditional release of contaminated properties was calculated to be 2300 cpm on average and 23 000 cpm at the highest-contamination part. The calculated numerical values of the operational levels are effective as long as the typical GM survey meter is used in the radiation measurement.