Health Physics

Bronson, Frazier L.

doi: N/Apmid: N/A

1994 marked the 35th Anniversary of the founding of the American Board of Health Physics (ABHP) by the Health Physics Society. This paper attempts tn identify the major elements in the evolution of the ABHP and, where possible, the individuals) responsible through 1993. Areas discussed include the implementation of the ABHP by the first few Boards, the duties of the examination panels, the evolution of the various examinations, the development of the recertification program, the economic factors in ABHP operations, and the birth of the American Academy of Health Physics.

Young, Robert W.

doi: N/Apmid: N/A

Traditionally, dose-response modeling has been on a strict experiment-by-experiment basis. Such an approach greatly restricts understanding of complex biological systems affected by numerous confounding factors that individually vary from experiment to experiment. In contrast, work described in this manuscript relies on a new analytical process (that considers both pooled and experiment-specific considerations) that was used to jointly analyze the bone marrow cell kinetics from a large data base on six species of test animals irradiated by protracted schedules of ionizing photon radiations. From this approach, we have modeled how the human LD

Bhat, I. S.

doi: N/Apmid: N/A

The work reported here deals with the study of interception and translocation of airborne

Mis, F. J.

doi: N/Apmid: N/A

Calculations of Committed Effective Dose Equivalent (CEDE) due to inhalation using four of the five methods suggested in the United States Nuclear Regulatory Commission Regulatory Guide 8.34 (1992a) were performed to determine if any significant differences in the calculated value of the CEDE exist for typical power plant radionuclides. These four methods included dose conversion factors from the United States Environmental Protection Agency Federal Guidance Report No. 11 (Eckerman et al. 1988), Annual Limit on Intake, Derived Air Concentrations, and Weighted Committed Dose Equivalents from ICRP Publication 30 (1979). Of the 68 radionuclides included, 48 demonstrated significant differences of 20% or greater in the calculated CEDE values for the four methods used. The differences in calculated values for the CEDE can be explained by the varied use of the 10% Rule and by rounding of tabulated values for ALIs and DACs to one significant digit.

Wise, Keith N.

doi: N/Apmid: N/A

This note describes an Electron Gamma Shower code (EGS4) Monte Carlo program for calculating radiation transport in adult males and females from internal or external electron and gamma sources which requires minimal knowledge of organ geometry. Calculations of the dose from planar gamma fields and from computerized tomography illustrate two applications of the package.

Short, Robert A.

doi: N/Apmid: N/A

Human tissues, obtained at autopsy from 82 volunteer donors with a history of occupational exposure, were analyzed for

Repin, Victor S.

doi: N/Apmid: N/A

Some radiation-emergency countermeasures, including evacuation, were implemented in the settlements of the 30-km zone during the early phase of the accident at the Chernobyl Nuclear Power Plant. These countermeasures are described and compared with the international recommendations. An analysis of the effectiveness of the emergency countermeasures was conducted based upon the results of a wide-scale public survey. Quantitative assessments of the effectiveness (dose reduction) of the countermeasures were derived.

Reif, R. H.

doi: N/Apmid: N/A

Dissolution rates of thorium from the uranium mill tailings piles at two Department of Energy Uranium Mill Tailings Remedial Action Project (UMTRAP) sites have been evaIuated. The thorium dissolution rates were evaluated in vitro using simulated lung fluid. The former uranium mills at the UMTRAP sites employed different chemical processes (acid leach and alkaline pressure leach) to extract the uranium from the ore, and the thorium dissolution rates at these sites were found to be markedly different. A site specific annual limit on intake (ALI) value for

Ueno, Kaoru

doi: N/Apmid: N/A

Moore, R.

doi: N/Apmid: N/A

The CAP-88 environmental radiological assessment computer code was benchmark tested to establish confidence in its results. The results from CAP-88 were compared to the results from the GENII computer code, which has undergone rigorous testing. The codes were benchmarked using 1990 and 1991 monitored atmospheric releases from Idaho National Engineering Laboratory facilities and the results (the effective dose equivalent to the maximally exposed offsite individual) were quantitatively compared using a metric based on the uncertainty in the Gaussian plume model and terrestrial transport models. The results of the benchmark tests were within the 95% acceptance region specified in the test protocol. CAP-88 was found to overpredict effective dose equivalent relative to GENII for elevated releases, largely because CAP-88 calculates a larger atmospheric dispersion factor (x/Q) than does GENII using the same meteorological data. However, CAP-88 consistently underpredicted effective dose equivalent relative to GENII for ground-level releases. This was because CAP-88 accounts for the processes of plume depletion by dry and wet deposition while GENII does not account for these processes. The effect of depletion was tested and found to be most important for a ground-level release of a highly depositing species such as radioiodine which implies that acceptable benchmark results would be difficult to obtain for a highly depositing species.