https://www.cs.uic.edu/~tanyabw/research/pubs/Berger-WolfEtal_Sensors06.pdf

Discrete sensor placement problems in distribution networks

This report serves as a user’s manual for the first release of the Dose and Risk Calculation software, DCAL. DCAL consists of a series of computational modules, driven in either an interactive or a batch mode, for the computation of dose and risk coefficients. The system includes extensive libraries of biokinetic and dosimetric data and models representing the current state of the art. DCAL has unique capability for addressing intakes of radionuclides by non-adults. DCAL runs as 32-bit extended DOS and console application under Windows 95/98/NT/2000/XP. It is intended for users familiar with the basic elements of computational radiation dosimetry. Components of DCAL have been used to prepare EPA Federal Guidance Reports 12 and 13 and a number of publications of the International Commission on Radiological Protection. The dose and risk values calculated by this first release are consistent with those published in Federal Guidance Reports 12 and 13.

https://www2.epa.gov/sites/production/files/2015-02/documents/dcal-manual.pdf

User’s Guide to the DCAL System

The purpose of this study was to evaluate the therapeutic efficacy and limitations of α-particle-emitting radiolabeled compounds by means of 2-dimensional histological images and distribution of activity on a microscopic level. Methods: A microdosimetric approach based on histological images is used to analyze the therapeutic effectiveness of α-particle-emitting 211At and 213Bi conjugated to 201B monoclonal antibody (mAb), which is reactive with murine lung blood vessels for the treatment of EMT-6 lung tumor colonies in nude mice. Autoradiography images were used to define the tissue morphology and activity distribution within lung tissues. Two animal groups were studied: Group A consisted of animals bearing small tumors (

https://jnm.snmjournals.org/content/jnumed/44/5/792.full.pdf

Microdosimetric Analysis of α-Particle-Emitting Targeted Radiotherapeutics Using Histological Images

Uranium is a naturally occurring primordial radioactive element. Small amounts found in air, water, and food are regularly consumed and inhaled by humans. Even the military, medical, and industrial use of depleted uranium can affect humans. There is an appreciable retention of incorporated uranium in skeleton, kidneys, and liver, and a review of respective effective dose coefficients has been given by the International Commission on Radiological Protection (ICRP) in its "Publication 69"; however, data regarding retention in organs or tissues and rates of urinary and fecal excretion for different age groups are incomplete. Therefore, the present study provides retention data that have been calculated for uranium in all compartments and for urinary and fecal excretion, following acute and chronic injection and ingestion for six age groups. The calculations are based on the current ICRP biokinetic model for uranium, and the data can be plotted by using any mathematical software to obtain the retention data at any time after incorporation or to calculate the internal average organ dose induced by uranium provided that specific absorbed fractions are available. The dynamic relationship of the retention in plasma and blood after intravenously and orally administered uranium can easily be derived from the database for injection and ingestion. The calculated contents of uranium in organs or tissues (using the uranium concentration in foodstuffs published by UNSCEAR for Europeans) are compared with autopsy data available in the literature. According to this model, the whole body of a 75-year-old man contains 7 microg uranium, of which 76% is in the skeleton, 1% in the kidneys, and 2.1% in the liver.

Biokinetic modeling of uranium in man after injection and ingestion.

http://www.lcb.esalq.usp.br/publications/articles/2009/2009eiv35n3p614-618.pdf

Study of environmental burden of lead in children using teeth as bioindicator

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.

A.C. James

Papers

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