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N H Harley

Publications and source records attributed to N H Harley.

At least 19 recordsLinked to original sources

Calculation of the air concentrations of serially decaying nuclides--a new method applied to radon progeny.

A new calculation method is presented for determining the air concentrations of any serially decaying nuclides. This new method is easily incorporated into a Basic or spreadsheet program that is used to record the decay data. Specifically, the measurements were designed to illustrate radon progeny from a filter sample that is gross-alpha counted. The method is based on regressing the decay data, recorded in 1-min intervals, on the time after the end of sampling with an equation that describes the alpha activity as a function of the decay exponentials, e-lambdat. The results from both generated data and experimental filter samples were compared to the results obtained by two other well-known methods. All the methods give comparable estimates for the progeny air concentrations; non-linear regression and weighting by variances produces the smallest error estimates with the method presented here.

Air Pollutants, Radioactive↗

The 1999 Lauriston S. Taylor lecture--back to background: natural radiation and radioactivity exposed.

I am profoundly grateful for being chosen as the twenty-third presenter of the Lauriston S. Taylor Lecture, and I share this honor with a list of distinguished scientists, including my husband, who pay tribute to the premier leader in radiation protection. In 1938, Laurie was working for the National Bureau of Standards and chaired the Advisory Committee on X-ray and Radium Protection, a group of 8 persons, who set the pace for all forthcoming radiation standards. NBS had, since 1913, been standardizing essentially all of the radium offered for sale in the U.S., and the problem arose to revise the handbook on proper conditions for handling radium based on the then current knowledge. This resulted in Handbook 23 (1938) superseding the 1934 work. At the time Laurie was a scientist working in the measurements side of radiation and though he contributed much to that field, his name is inseparably linked with guidance in radiation protection. Today we pay tribute for his leadership that he carried out with intelligence, grace, and personal warmth. My talk today deals mostly with measured data for naturally occurring internal radiation emitters and how these data can be used for predictive purposes in estimating the dose and risk from internal body contamination. This stresses the "and Measurements" part of the Council's title. The topic of this year's NCRP Annual Meeting is "Radiation Protection in Medicine: Contemporary Issues." I believe that physicians and State and Federal agencies will have to cope with complaints following various exposure situations resulting from the cleanup of background radionuclides during closure at nuclear facilities, military use of radioactivity, and occurrences of high natural background in some locations. They will find comfort in the knowledge that existing background radiation data can be the basis for predictions of realistic dose and risk in most situations.

Background Radiation↗

A comparison between the localization of lung tumors in uranium miners and in nonminers from 1947 to 1991.

BACKGROUND: Lung cancer was noted to be increased in cigarette smoking miners and nonminers. Carcinogen particulates deposit differentially in the central, middle, and peripheral zones of the bronchial tree depending on the size of the particle. The object of this study was to evaluate the incidence of tumors; their cell types; and the relationship of particulate size to their position in the bronchial tree. METHODS: Tumor position in the bronchial tree was studied for a cohort of 467 uranium miners and 311 nonminers with lung cancer. RESULTS: An examination of all histologic subtypes showed that the proportion of lung cancers in the central zone was significantly greater in miners than in nonminers presumably due to the deposition of radon decay products attached to the silica dust particles. The higher percentage of central tumors in the miners was primarily due to the distribution of a greater proportion of squamous cell and small-cell tumors. The ratio of 0.75 for the central to middle and peripheral location for adenocarcinomas was much lower than for squamous cell and small-cell carcinomas with ratios of 1.4 and 7.3, respectively. In the mining cohort, there were ten times as many small-cell tumors in the central area as in the middle and peripheral regions, whereas, for the nonminers there were only five times as as many centrally located small-cell tumors as middle and peripheral (chi square is 7.0 degrees, P < 0.01). These data suggest that radon may be deposited preferentially to the central region of the lungs in uranium miners. CONCLUSIONS: Based on our observations of the differential positions of lung tumors in the bronchial tree for miners and nonminers and previous studies by others regarding size-dependent deposition of particulates in the bronchial tree, it is concluded that inhaled dust, radon, and cigarette smoke combine to form large particulates that deposit in the central bronchial tree. Filtered cigarette smoke or other small carcinogens from smaller particulates that deposit more peripherally.

Bronchial Neoplasms↗

Validation of a personal radon monitor for use in residential 22Rn exposure studies.

A personal radon monitor (PRM) has been developed and validated for use in studies of residential 222Rn exposure. A pilot study was performed in six New Jersey homes with elevated Rn concentrations. Occupants wore PRMs, and identical monitors were placed in many rooms of the home. Extensive assessment of PRM performance has been done. A simple model for personal Rn exposure has been tested and measured occupant exposures have been compared with stationary Rn measurements. The PRM works well, with precision limited by the counting error in the exposure range examined (2-100 kBq m-3 h). The PRM sensitivity is 2.2 kBq m-3 h, and its efficiency is 2.6 tracks (kBq m-3 h)-1 per 81 mm2 film.

Air Pollutants, Radioactive↗

Personal and home 222Rn and gamma-ray exposure measured in 52 dwellings.

A personal 222Rn and gamma-ray detector has been developed. The detector precision is limited only by the Poisson counting error and has a lower limit of detection in this study of 4.5 kBq m-3 h (4 pCi L-1 day). The detector was used in a study of 52 homes in Illinois to measure the personal exposure vs. the simultaneous exposure on all levels of the home. The ratio of personal exposure to basement 222Rn concentration averaged 0.22, with a high degree of scatter (R2 = 31%). The ratio of personal exposure to first floor 222Rn concentration was 0.71, with good correlation (R2 = 85%). In the absence of personal monitoring data, the best estimate of personal exposure appears to be from measurements in the first-floor living space of the home.

Air Pollutants, Radioactive↗

Methodology issues in risk assessment for radon.

The alpha dose per unit radon daughter exposure in mines and homes is comparable at about 5 mGy/WLM. This means that excess lung cancer risk determined in follow-up studies of miners should be valid to extrapolating to environmental populations. There are several models currently used for risk projection to estimate lung cancer in the U.S. from indoor radon exposure. The accuracy of the estimates depends upon the quality of the exposure data and the models. Recent miner epidemiology confirms that excess lung cancer risk decreases with time subsequent to cessation of exposure. The most rigorous ecological study, to date, shows a persistent negative relationship between average measured indoor radon in U.S. counties and lung cancer mortality. A model for lung cancer risk is proposed that includes smoking, urbanization, and radon exposure. The model helps to explain the difficulties in observing the direct effects of indoor radon in the environment.

Dose-Response Relationship, Radiation↗

An improved 222Rn canister using a two-stage charcoal system.

A prototype for an improved passive 222Rn canister (R-Canister) was designed and compared to conventional charcoal canisters for its adsorptive and desorptive characteristics following exposures to 222Rn at 23 degrees C in the presence of water vapor. The R-Canister, containing a two-stage charcoal system, minimizes the adverse effects of water vapor by maintaining the amount of adsorbed water vapor in the primary Rn adsorbent below the "break-point" of the charcoal. This is achieved by the placement of a desiccant charcoal cartridge 6 cm above the primary Rn adsorbent. The optimal bed depth of the primary adsorbent, determined from a diffusion study, was found to be 2.3 cm. The measured value for the effective diffusion coefficient of RN in a peat-based charcoal at 15% humidity and 25 degrees C is 7.97 x 10(-10) m2 s-1. Exposures to 70% humidity for 7 d increased the buildup time-constant of Rn in the R-Canisters by 33% as compared to R-Canisters exposed to 15% humidity. At relative humidities ranging from 15-70%, the 222Rn buildup time-constant of the R-Canister ranged from 43-94 h, whereas the desorption time-constant ranged from 46-64 h. Typical buildup time-constants and desorption time-constants for conventional fully-opened charcoal canisters currently in field use ranged from 30-43 h and 17-29 h, respectively, over the same range of humidities.

Air Pollutants, Radioactive↗

Adsorption and desorption of noble gases on activated charcoal: I. 133Xe studies in a monolayer and packed bed.

Detailed desorption studies using petroleum-based activated charcoals were conducted in monolayers and packed beds. Less extensive studies were conducted on several other types of charcoal. Kinetic studies, using 133Xe, demonstrated the existence of a micropore volume with entrance capillaries that together determined the response characteristics of charcoal to external concentration gradients of tracer gases. This new two-phase model, composed of micropores and entrance capillaries, describes the desorption dynamics of an adsorbed gas in the presence of water vapor. Condensed water vapor in the entrance capillaries of the charcoal reduced the effective pore radius and increased the diffusion half-time. Water could also adversely affect the integrating capability of the charcoal dramatically if the adsorbed water completely blocked the entrance capillaries. The amount of adsorbed water required to block the capillaries varied with the charcoal type and was termed here as the "break-point." The desorption parameters measured in this work can be used to design an improved passive Rn monitor to effectively integrate during a 3-7 d exposure period by eliminating the adverse effects of water vapor. The improved canister design would provide more accurate and reproducible measurements of indoor Rn concentrations than are currently available.

Adsorption↗

Adsorption and desorption of noble gases on activated charcoal: II. 222Rn studies in a monolayer and packed bed.

The adsorptive and desorptive characteristics of canisters containing a petroleum-based charcoal were investigated under controlled conditions of temperature, relative humidity, and Rn concentration. Charcoals exposed in a monolayer and packed bed during exposure intervals of 1-7 d demonstrate that Rn adsorption and desorption are dependent on bed depth and the amount of water adsorbed. Changes in the adsorptive and desorptive properties of the charcoal occurred near the break-point where the pores became occluded by water vapor that condenses in the entrance capillaries. Radon-222 adsorption is decreased by an order of magnitude as the amount of adsorbed water exceeds the break-point of the charcoal. The reduction in pore surface due to adsorbed water results in a marked increase in the rate of Rn loss from exposed canisters, accounting for reduced adsorption. The apparent desorption time-constant for a 2-cm bed of loose Witco 6 x 10 mesh charcoal containing 0.220-0.365 kg H2O kg-1 is typically between 2-8 h. The apparent desorption time-constant for an equivalent packed bed containing a water vapor content of 0.026-0.060 kg H2O kg-1, which is below the break-point of the charcoal, is about 15-30 h. Conventional charcoal canisters, if exposed in the fully-opened configuration, can achieve the break-point in less than 4 d at 70% humidity. The use of a diffusion barrier would allow for longer exposure times until the break-point of the charcoal is achieved.

Adsorption↗

Measured intake and excretion patterns of naturally occurring 234U, 238U, and calcium in humans.

The normal dietary and fluid intake and urinary and fecal excretion of 234U and 238U were determined in humans under strictly controlled conditions in the Metabolic Research Ward at Hines Hospital. These values formed the basis of the metabolic balances of these uranium isotopes. The major pathway of 234U and of 238U excretion was via the intestine while the urinary 234U and 238U were very low, averaging 2% of the total excretion. The uranium balances were roughly in equilibrium. These data were used in combination with measurements of tissue concentrations of uranium from nonoccupationally exposed humans to calculate steady-state uptake factors for environmental exposure to uranium isotopes during baseline conditions of a normal dietary intake.

Animals↗

Determining the charged fractions of 218Po and 214Pb using an environmental gamma-ray and Rn detector.

The rate of 218Po and 214Pb atoms collected electrostatically inside an environmental gamma-ray and 222Rn detector (EGARD) was measured. These measurements were used to directly infer the charged fraction of 218Po and to calculate the charged fraction of 214Pb. Thirty-two percent of the 218Po was collected electrostatically using approximately -1500 V on a 2.54 cm diameter Mylar covered disc inside a vented A1 EGARD of 1 L volume. About 91% of the 214Pb is collected electrostatically under the same conditions. The measurements were performed in a calibrated 222Rn test chamber at the Environmental Measurements Laboratory (EML) using the Thomas alpha-counting method with 222Rn concentrations averaging about 4300 Bq m-3. The atomic collection rates were used with other measured quantities to calculate the thermoluminescent dosimeter (TLD) signal acquired from EGARD for exposure to 1 Bq m-3 of 222Rn. The calculations account for 222Rn progeny collection using a Teflon electret and alpha and beta detection using TLDs inside EGARD. The measured quantities include the energies of 218Po and 214Po alpha-particles degraded by passage through the 25 microns thick electret. The TLD responses to these alpha- and beta-particles with an average energy approaching that obtained from the combined spectra of 214Pb and 214Bi were also measured. The calculated calibration factor is within 30% of the value obtained by exposing EGARD to a known concentration of 222Rn. This result supports our charged fraction estimates for 218Po and 214Pb.

Air Pollutants↗