Practical experience of the application of ICRP models in internal dose assessment.

The introduction of the Ionising Radiations Regulations 1999 in the UK, which came into force on 1 January 2000, led to significant changes in internal dose assessment. Before this date, assessments were based on the methodology from ICRP Publication 26 and, in general, made use of simple models such as those detailed in ICRP Publication 30. However, the introduction of the new Regulations required the use of ICRP Publication 60 methodology, and, at the same time, the latest ICRP biokinetic models were introduced. Many of these newer models were considerably more complex than the ones they replaced. In particular, the use of 'recycling', where activity is constantly recirculated between different organs, meant that the models could not simply be implemented by use of the Skrable formula, as detailed in ICRP Publication 30. This paper outlines two aspects of the application of these latest ICRP models. First, the problems encountered during implementation of these models are detailed, and secondly, it covers the practical experience of using the resulting computer programs for internal dose assessment.

IMBA Expert: internal dosimetry made simple.

In 1997, a collaboration between British Nuclear Fuels plc (BNFL), Westlakes Research Institute and NRPB started, with the aim of producing IMBA (Integrated Modules for Bioassay Analysis), a suite of software modules that implement the new ICRP models for estimation of intakes and doses. This was partly in response to new UK regulations, and partly due to the requirement for a unified approach in estimating intakes and doses from bioassay measurements within the UK. Over the past 5 years, the IMBA modules have been developed further, have gone through extensive quality assurance, and are now used for routine dose assessment by approved dosimetry services throughout the UK. More recently, interest in the IMBA methodology has been shown by the United States Department of Energy (USDOE), and in 2001 an ambitious project to develop a software package (IMBA Expert USDOE Edition) which would meet the requirements of all of the major USDOE sites began. Interest in IMBA Expert is now being expressed in many other countries. The aim of this paper is to outline the origin and evolution of the IMBA modules (the past); to describe the full capabilities of the current IMBA Expert system (the present) and to indicate possible future directions in terms of capabilities and availability (the future).

UK laboratory intercomparison on internal dosimetry.

A laboratory intercomparison for internal dose assessment from a variety of intake scenarios is described. This is the first UK intercomparison using the revised ICRP Human Respiratory Tract and biokinetic models. Four United Kingdom laboratories participated and six cases were assessed. Overall, the agreement in internal dose assessments between laboratories was considered satisfactory with 79% of the assessed committed effective doses, e(50), for cases within a band of +/- 40% of the median value. The range (highest/lowest) in e(50) estimated by the laboratories was smallest (1.2) for a case involving inhalation of 137Cs. The range was greatest (6.0) for a case involving a wound with, and possible inhalation of, 238Pu, 239Pu and 241Am; the variation between laboratories in assessment of intakes could not be considered to be satisfactory in this case. Judgements on the most appropriate data to use in estimating intakes, choice of parameter values for use with the ICRP models and allowing for the effects of treatment with DTPA were important sources of variability between laboratories.

The assessment of organ doses from plutonium for an epidemiological study of the Sellafield workforce.

An epidemiological study of mortality and cancer rates in plutonium workers at the Sellafield nuclear installation has been carried out by researchers at the London School of Hygiene and Tropical Medicine. The study required the assessment of organ-specific doses from plutonium for more than 5000 workers over a period of 40 years. This was a major undertaking as it involved the reconstruction of annual received doses from the results of some 223,000 urine samples that had been provided by the workers in the study. This paper outlines the techniques and strategies adopted in order to generate best estimates of dose from the available data, and presents summaries of these doses.