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The paper describes how the programme of individual monitoring (IM) of internal exposure (IE) at Shelter object (SO) was designed and what results were obtained in the framework of the programme for 5 y. The main dose-forming factors of IE at SO are intakes of radionuclides of transuranium elements, 90Sr and 137Cs. During designing the IM of IE programme, the contribution of each radionuclide was estimated for different types of works and intake paths. The different types of direct and indirect biophysical measurements that could be used for the purposes of IM of IE were analysed. The control of 239+240Pu content in faecal samples was chosen as a basic type of control of IE. ‘Dose per unit content’ functions were used for the justification of the IM of IE programme; also, they were used for the assessment of doses of personnel at SO. [ABSTRACT FROM PUBLISHER]

The objective of this Task Group is the coordination of research studies on biokinetic models and the evaluation of the implications of new biokinetic models on dose assessment and safety standards. For this the new ICRP models, which will be used for a revision of ICRP Publications 30, 54, 68 and 78, are implemented into six different computer codes in five European countries and quality assured by intercomparison procedures. The work has started with the implementation of the new ICRP Alimentary Tract Model. New systemic models and the new NCRP wound model will follow. The work also includes the evaluation of experimental results in terms of formulation by the new model structures and a quality assurance of model formulation. [ABSTRACT FROM AUTHOR]

The 'Individual Monitoring for Internal Exposure' (IMIE) computer codes are the family of interactive tools for interpretation of the bioassay data and individual dose assessments. During 10 y of the IMIE evolution, the extensive experience in the IMIE application has been accumulated and the underlying methodology has undergone essential improvements. The main distinguished feature of the IMIE ideology is the automated numerical analysis of all examined exposure scenarios with the succeeding interactive identification of events of intake(s) and assessment of associated doses. The numerical deconvolution algorithms and the massive library of tabulated 'bioassay/dose response functions' are employed for the processing of an arbitrary pattern of intake and complex exposure conditions. This article discusses details implemented in the IMIE algorithms and examples of IMIE application. [ABSTRACT FROM AUTHOR]

In the scope of the IDEAS project to develop General Guidelines for the Assessment of Internal Dose from Monitoring data, two databases were compiled. The IDEAS Bibliography database contains references dealing with problems related to cases of internal contamination. The IDEAS Internal Contamination Database now contains more than 200 cases of internal contamination. In the near future, the IDEAS Internal Contamination database will be made available to the internal dosimetry community. The database has several potential applications, including: training, testing biokinetic models, testing software for calculating intakes and doses from bioassay data, comparison of data from a new accidental intake with that from previous exposures to similar materials. The database is by no means complete, and this presentation is also an appeal for internal contamination cases to extend and update it. [ABSTRACT FROM AUTHOR]

In recent major international intercomparison exercises on intake and internal dose assessments from monitoring data, the results calculated by different participants varied significantly. Based on this experience the need for harmonisation of the procedures has been formulated within an EU 5th Framework Programme research project. The aim of the project, IDEAS, is to develop general guidelines for standardising assessments of intakes and internal doses. The IDEAS project started in October 2001 and ended in June 2005. The project is closely related to some goals of the work of Committee 2 of the ICRP and since 2003 there has been close cooperation between the two groups. To ensure that the guidelines are applicable to a wide range of practical situations, the first step was to compile a database of well-documented cases of internal contamination. In parallel, an improved version of an existing software package was developed and distributed to the partners for further use. A large number of cases from the database was evaluated independently by the partners and the results reviewed. Based on these evaluations, guidelines were drafted and discussed with dosimetry professionals from around the world by means of a virtual workshop on the Internet early in 2004. The guidelines have been revised and refined on the basis of the experiences and discussions in this virtual workshop. The general philosophy of the Guidelines is presented here, focusing on the principles of harmonisation, optimisation and proportionality. Finally, the proposed Levels of Task to structure the approach of internal dose evaluation are reported. [ABSTRACT FROM AUTHOR]

Simultaneous analysis here of urine data from both workers gave I f i SB r sb = 0.004, I s i SB s sb = 2 × 10 SP -4 sp d SP -1 sp , and assignment to Type S. (82) [553] assessed the airborne and internal aluminium exposure of 12 aluminium welders and fitters in a shipyard and five manufacturers of aluminium sulphate. Nevertheless, for each element, a default absorption type is recommended for use in the absence of information on which the exposure material can be assigned to Type F, M, or S. For most elements, Type M is recommended by default, including all of those in OIR Part 5 except the halogens (Type F) and aluminium (Type S). When comparing the bioavailability of orally gavaged aluminium citrate, nitrate, chloride, sulphate, and hydroxide in rats for 7 or 14 d, [528] noted few differences in blood and tissue concentrations, except for significantly higher aluminium content in rats gavaged with aluminium citrate. (90) As explained above, [471] monitored aluminium in urine and plasma, and airborne aluminium in the workplace of seven workers exposed to aluminium dust from polishing and shape cutting, or to aluminium welding fumes for 6 months. [Extracted from the article]

Nuclear installations may contain a large inventory of radioactive material and an emergency caused by an accident, natural disaster, or malevolent act may cause uncontrolled releases of radionuclides to the environment. The paper presents a brief overview of individual radiological monitoring in case of major releases of radionuclides to the environment and introduces the new Report 92 of the International Commission on Radiation Units and Measurements (ICRU) on Radiation Monitoring for Protection of the Public after Major Releases of Radionuclides to the Environment. The Report was prepared taking into account the results of the research «Development of the program for radiation and hygienic monitoring for the radiological protection of human under radiation accidents and acts of nuclear terrorism» which was carried out in the internal dosimetry laboratory of the NRCRM of NAMS of Ukraine in 2016-2018. The Report Committee was headed by the scientific supervisor of the research, the Committee consisted of leading experts from UK, Italy, China, Germany, Russia, Slovenia, United States, Ukraine, Japan, and experts from the International Atomic Energy Agency. The preparation of the Report was supported by the US Environmental Protection Agency, US Nuclear Regulatory Commission, US Department of Energy, National Academy of Medical Sciences of Ukraine, and Radiation Protection Institute of the ATS of Ukraine., (V. Berkovski, G. Ratia, Yu. Bonchuk.)

Research on iodine metabolism was reviewed with special reference to short-term processes, pregnancy, and lactation. A detailed discussion of the new physiologically-oriented biokinetic model and a model parameterization procedure are given. Predictions of the new model are applicable for the analysis of in vivo and in vitro clinical data gained using iodine or radioactive tracers, as well as for the assessment of radiation exposure doses to mothers and offspring. The model can be used to simulate biokinetic processes in the human body, for prediction of biokinetic parameters such as the time course of thyroid uptake (both for mother and fetus), the rate of exertion with urine, and the level of iodine secretion with saliva and breastmilk. The structure of the model is applicable in a wide range of stable iodine in the diet, both for pregnant and non-pregnant persons.