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Biomedical subjects

A Birchall

Publications and source records attributed to A Birchall.

At least 19 recordsLinked to original sources
PubMed2006

IMBA Professional Plus: a flexible approach to internal dosimetry.

IMBA (Integrated Modules for Bioassay Analysis) is a suite of software modules that implement the current ICRP biokinetic and dosimetric models for estimation of intakes and doses. The IMBA modules have gone through extensive quality assurance, and are now used for routine formal dose assessment by Approved Dosimetry Services throughout the UK. HPA has continued to develop the IMBA modules. In addition, several projects, sponsored by organisations both in the USA and in Canada, have resulted in the development of customised user-friendly interfaces (IMBA Expert 'editions'). These enable users not only to use the standard ICRP models, but also to change many of the parameter values from ICRP defaults, and to apply sophisticated data handling techniques to internal dose calculations. These include: fitting measurement data with the maximum likelihood method; using multiple chronic and acute intakes; and dealing with different data types, such as urine, faces and whole body simultaneously. These interfaces were improved further as a result of user-feedback, and a general 'off-the-shelf' product, IMBA Professional, was developed and made available in January 2004. A new version, IMBA Professional Plus, was released in April 2005, which is both faster and more powerful than previous software. The aim of this paper is to describe the capabilities of IMBA Professional Plus, and the mathematical methods used.

Algorithms↗
PubMed2006

Obtaining an unbiased estimate of intake in routine monitoring when the time of intake is unknown.

A common problem in internal dosimetry occurs in routine monitoring, when it is required to estimate an intake from a measurement made at the end of a monitoring interval, and the time of intake is unknown. ICRP suggests that, in these cases, it should be assumed that the intake occurred in the middle of the monitoring period. However, it has been shown that this will, in the long term, lead to biased estimates of a worker's intake and dose. In order to overcome this biasing, the United States Department of Energy (USDOE) recommends a different method based on calculating the intakes for all possible intake-times in the interval, and then taking an arithmetic average. In this paper, it is shown that both the ICRP and USDOE methods are biased. An alternative method is suggested, which assumes a constant chronic intake throughout the monitoring interval. Monte Carlo simulations are used to estimate the magnitude of bias for two realistic monitoring programmes using all three methods. It is shown that the proposed method is unbiased and also yields estimates of intake that are generally closer to the actual intake, than the other two. The Monte Carlo conclusions are backed up by a theoretical analysis of bias. Finally, the source of bias in the apparently intuitive approach of the USDOE method is revealed by viewing the problem from a Bayesian perspective.

Algorithms↗
PubMed2006

Uncertainties in doses from intakes of radionuclides assessed from monitoring measurements.

The evaluation of uncertainties in doses from intakes of radionuclides is one of the most difficult problems in internal dosimetry. In this paper, the process of assessing internal doses from monitoring measurements is reviewed and the major sources of uncertainty are discussed. Methods developed independently at HPA and at IRSN for the determination of uncertainties in internal doses assessed from monitoring measurements are described. Both use a Monte Carlo simulation approach. Results are described for three illustrative examples. An alternative method developed at the Los Alamos National Laboratory that uses Bayesian statistical methods is also described briefly.

Animals↗
PubMed2003

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.

Body Burden↗
PubMed2003

The ICRP working party on bioassay interpretation.

In recent years there have been many developments in modelling the behaviour of radionuclides in the human body. The current generation of models is designed to be more 'realistic' than the previous generation of simple compartment models. The International Commission on Radiological Protection (ICRP) uses these models to produce dose coefficients and recognises that there is a need to give more guidance on how these models can be used to interpret bioassay data. A working party has been set up to address the issue. This paper describes some of the problems, some approaches to solving the problems and the progress of the ICRP working party.

Advisory Committees↗
PubMed2003

Review of methods and computer codes for interpretation of bioassay data.

Internal dose determination is an essential component of individual monitoring programmes for workers or members of the public exposed to radionuclides, and methods and computer programs are required for dose assessment. A recent international European Radiation Dosimetry Group (EURADOS) intercomparison has shown unacceptably large ranges in the results assessment. An ICRP working party has been initiated to consider what guidance ICRP can give on the use of models and interpret bioassay data in terms of intake/dose. In this field, six codes for bioassay data interpretation, which implement the current ICRP publication 78 biokinetic models, have been reviewed against several criteria with different levels of importance: minor criteria such as the practical use of the code and the graphical capabilities, and major criteria such as the choice of available parameters, peculiarities of data fitting and interpretation, the choice of biokinetic models and the use of uncertainties. All these criteria were assessed using one artificial set of data and two examples extracted from the previous international EURADOS intercomparison.

Administration, Oral↗
PubMed2003

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).

Computer Simulation↗
PubMed2002

Uncertainty analysis of the weighted equivalent lung dose per unit exposure to radon progeny in the home.

A parameter uncertainty analysis has been performed to derive the probability distribution of the weighted equivalent dose to lung for an adult (w(lung) H(lung)) per unit exposure to radon progeny in the home. The analysis was performed using the ICRP Publication 66 human respiratory tract model (HRTM) with tissue weighting factor for the lung, w(lung) = 0.12 and the radiation weighting factor for alpha particles, wR = 20. It is assumed that the HRTM is a realistic representation of the physical and biological processes, and that the parameter values are uncertain. The parameter probability distributions used in the analysis were based on a combination of experimental results and expert judgement from several prominent European scientists. The assignment of the probability distributions describing the uncertainty in the values of the assigned fractions (ABB, Abb, AAI) of the tissue weighting factor proved difficult in practice due to lack of quantitative data. Because of this several distributions were considered. The results of the analysis give a mean value of w(lung) H(lung) per unit exposure to radon progeny in the home of 15 mSv per working level month (WLM) for a population. For a given radon gas concentration, the mean value of w(lung) H(lung) per unit exposure is 13 mSv per 200 Bq.m(-3).y of 222Rn. Parameters characterising the distributions of w(lung) H(lung) per unit exposure are given. If the ICRP weighting factors are fixed at their default values (ABB, Abb, AAI = 0.333, 0.333, 0.333; w(lung) = 0.12; and wr = 20) then on the basis of this uncertainty analysis it is extremely unlikely (P approximately 0.0007) that a value of Hw/Pp for exposure in the home is as low as 4 mSv per WLM, the value determined with the epidemiological approach. Even when the uncertainties in the ABB, Abb, AAI, values are included then this probability is predicted to be between 0.01 to 0.08 depending upon the distribution assumed for describing the uncertainties in the ABB, Abb, AAI, values. Thus, it is concluded that the uncertainties in the HRTM parameters considered in this study cannot totally account for the discrepancy between the dosimetric and epidemiological approaches.

Administration, Inhalation↗
PubMed2002

Experimental determination of the absorption rate of unattached radon progeny from respiratory tract to blood.

An exposure methodology was developed for the determination of the absorption rate of unattached radon progeny deposited in the human respiratory tract to blood. Twenty-one volunteers were exposed in a radon chamber during well-controlled aerosol and radon progeny conditions, with predominantly unattached radon daughters. Special efforts were made to restrict the dose to the volunteers to an absolute maximum of 0.08 mSv. Measurements of radon gas and radon progeny in blood samples of these volunteers indicated absorption half times of 20 min to 60 min. Former determinations, mainly performed with much larger aerosol particles of diameters between 100 nm and 1,000 nm, implied absorption half times around 10 h. This indicates that the absorption of radon decay products from ciliated airways into blood is dependent upon particle size and particle composition.

Absorption↗
PubMed2001

In vivo measurement of unattached radon progeny deposited in the human respiratory tract.

Seven nose breathing and seven mouth breathing volunteers were exposed to atmospheres enriched with unattached radon progeny (218Po, 214Pb and 214Bi). The activity of these radionuclides deposited in the respiratory tract was measured in vivo after the exposures. The results of these measurements are in agreement with predictions calculated with the ICRP Publication 66 Human Respiratory Tract Model. Temporal analysis of the activity deposited in the heads of the volunteers leads to the conclusion that a significant amount of the deposited activity associated with particle diameters of about 1 nm is not subject to a fast transport to the gastrointestinal tract as generally reported for larger aerosol particles.

Administration, Inhalation↗
PubMed1999

The normal range for inter-arm differences in blood pressure.

OBJECTIVE: to establish the mean and normal range for the difference in simultaneous systolic and diastolic blood pressure measurements between the right and left arm. SUBJECTS: 462 subjects, age range 20-89 years, in sinus rhythm and with no history of stroke, 98 of whom had a history of cardiovascular disease or were taking vasoactive medication. METHODS: four simultaneous recordings of blood pressure in both arms were made using two automated sphygmomanometers with the subject supine after resting for 10 min. RESULTS: inter-arm systolic and diastolic blood pressure differences show a near normal distribution of values. Some individuals had clinically important differences in systolic and diastolic blood pressure between their arms. The magnitude of these differences was not related to the mean baseline blood pressure. Linear regression analysis did not demonstrate any significant relationship between inter-arm systolic or diastolic blood pressure difference and age in patients of either sex. For systolic blood pressure the mean difference between the right and left arm was 1.1 mmHg and the normal range was -9 mmHg to 11 mmHg. For diastolic blood pressure the mean difference was 0 mmHg and the normal range -10 mmHg to 10 mmHg. CONCLUSION: the frequency of significant inter-arm systolic and diastolic blood pressure differences suggests that the blood pressure should be taken in both arms at the initial consultation. At subsequent visits, the arm in which measurements are taken should be recorded in the case notes. The higher of the two readings should be used to guide further management decisions.

Adult↗
PubMed1995

Implications of airway retention for radiation doses from inhaled radionuclides.

A slow phase of bronchial and bronchiolar clearance ('airway retention') has been included in the revised dosimetric model for the human respiratory tract recently adopted by the International Commission on Radiological Protection (ICRP), based primarily on the results of the bolus clearance experiments conducted by Stahlhofen et al. The treatment of airway retention in the new ICRP model is described. An analysis was carried out of the sensitivity of the equivalent lung dose, and the effective dose, to assumptions made in the new model about the extent of airway retention. It was shown that inclusion of airway retention of material deposited in the bronchial tree does have a significant effect on both end-points (of the order of 10-50%) for a wide range of radionuclides. In some cases, notably moderately soluble forms of long-lived alpha-emitters, its inclusion increases these doses by up to a factor of three, so that it makes the dominant contribution to the calculated dose. The model assumes that material in transit through the bronchial tree, having initially deposited in the alveolar region, is not subject to airway retention. Including retention of this material would typically increase doses by a further factor similar to that resulting from the airway retention of the bronchial deposit.

Absorption↗
PubMed1994

A rapid method for modeling the kinetics of radioactive progeny applied to thorium in the lungs.

A general method for solving first-order compartmental models (recycling and nonrecycling) with any number of radioactive progeny is described and a heuristic proof of the method is provided. The method can be applied to any system where the progeny are assumed to behave isokinetically with the parent, as is the case with the biokinetic models currently recommended by the ICRP. The method is simple to apply, and its application to the modeling of radioactive progeny in the lungs following inhalation of thorium oxides is illustrated. The new ICRP respiratory tract model is used for this illustration.

Humans↗
PubMed1989

A microcomputer algorithm for solving first-order compartmental models involving recycling.

A general algorithm for solving first-order compartmental models including recycling systems has been developed and its implementation on a microcomputer is described. Matrix algebra is used to obtain for any compartmental model an analytical solution, which is expressed as the exponential of a matrix of rate constants. A special technique is used in the algorithm to enable this exponential to be evaluated with a rapidly converging series. Truncation errors incurred in this process are estimated automatically. Thus, in an extreme case, where these errors may be significant, the appropriate action can be taken. Given a particular model, the user enters the model parameters into a rate matrix according to a simple rule. The algorithm then uses this matrix to solve the model, and thus no specialized mathematical knowledge is needed. The algorithm is given in a short BASIC program (60 lines) listed in an appendix. No additional software is required. By running this program on a standard microcomputer, the user can solve models of any complexity: those up to 15 compartments in seconds and those up to 30 compartments within a minute. The algorithm is thus ideally suited to solve kinetic models describing the transport of radionuclides in the environment or the translocation of elements in biological systems such as the metabolic models recommended by the International Commission on Radiological Protection (ICRP). Given the initial amount of material in each compartment at time t = 0, together with its radioactive decay constant, the algorithm gives both the amount in each compartment at any future time t and the number of disintegrations that will have occurred in each compartment up to time t. The computer program, shown in an appendix, could easily be used to calculate disintegrations over any time interval of interest, or to predict the quantities or fractions of an intake expected to be present in any in vivo or excretion compartments of interest. Thus, the algorithm can be useful in both the design and conduct of bioassay and internal dose assessment procedures.

Algorithms↗
PubMed1989

Sensitivity testing of an age-related, multicompartment dosimetric model for bone-surface-seeking radionuclides in man.

The sensitivity testing of an age-related dosimetric model and its application to the dosimetry of 239Pu are described. The model is used to calculate the committed dose received by the skeleton and liver to age 70 y, following intakes of 239Pu by an adult aged 20 y and by children aged 0 and 10 y. The model is biologically based and takes account of the age-dependent transfer of Pu between the different organs of the body and between the different components of the skeleton. It consists of 22 compartments, 16 of which are skeletal, each connected by transfer pathways defined by age-dependent rate constants. The sensitivity of the predictions of the model, as applied to adults, to changes in the assumed values of rate constants were tested. The results of the tests applied suggested that the age-related model is relatively robust and is not particularly sensitive to changes in the assumed values of many of the rate constants used.

Adult↗
PubMed1989

The current approach of the ICRP Task Group for modeling doses to respiratory tract tissues.

For radiation protection purposes, the International Commission on Radiological Protection (ICRP) Task Group proposes to apportion radiation risk within the respiratory tract according to the tumor mortality rates observed in the different anatomical regions. This approach requires that doses absorbed by extrathoracic tissues must be considered, in addition to those in the lung. For the extrathoracic region, the tissues at highest potential risk are the pharyngeal parts of the nasopharynx and oropharynx and a part of the larynx. In the lung, all tissues are potentially at risk, and it is necessary to consider doses absorbed by bronchial tissues, the lung parenchyma, and lymph nodes. This paper outlines the methods proposed by the Task Group to evaluate the heterogeneous doses absorbed by sensitive cells in these tissues from radioactive decays of alpha-emitters. The objective is to evaluate doses to broad regions of the respiratory tract, where the regions are defined to reflect substantial differences in potential risk when taking into account deposition and clearance behavior. The Task Group proposes to represent the respiratory tract by three generic regions: an extrathoracic region and two thoracic regions, one clearing fast and one slowly. The models of aerosol deposition and clearance applied for each region are outlined. To illustrate the use of the model, doses are evaluated for the key cases of short-lived radionuclides and long-lived insoluble alpha-emitters and are discussed with regard to current ICRP recommendations.

Aerosols↗