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Modelling of radiation field around spent fuel container.

Operation of nuclear reactors leads to the production of spent nuclear fuel (SNF). There are two basic strategies of SNF management: ultimate disposal of SNF in geological formations and recycle or repeated utilisation of reprocessed SNF. In both options, there is an urgent necessity to study radiation properties of SNF. Information about SNF radiation properties is required at all stages of SNF management. In order to reach more effective utilisation of nuclear materials, new fuel cycles are under development based on uranium-plutonium, uranium-thorium and some other types of nuclear fuel. These promising types of nuclear fuel are characterised by quite different radiation properties at all the stages of nuclear fuel cycle (NFC) listed above. So, comparative analysis is required for radiation properties of different nuclear fuel types at different NFC stages. The results presented here were obtained from the numerical analysis of the radiation field around transport containers of different SNF types and in SNF storage. The calculations are carried out with the application of the computer code packages SCALE-4.3 and MCNP-4C. Comparison of the dose parameters obtained for different models of the transport container with experimental data allowed us to make certain conclusions about the errors of numerical results caused by the approximate geometrical description of the transport container.

Computer Simulation↗

Unexpectedly high activity of 228Th in excretion samples following consumption of Brazil nuts.

A worker provided a routine faecal sample for plutonium and americium analysis. In the course of this analysis 500 mBq of (228)Th was discovered. There seemed no credible occupational route for intake of thorium. Further investigation revealed that the worker consumed approximately 25 g d(-1) of nuts, including Brazil nuts. A sample of these nuts was analysed and found to contain activities of (228)Th in sufficient quantity to account for the faecal activity. However, follow-up urine samples taken from the worker showed 0.6-0.7 mBq of (228)Th. The intake of (228)Th via nuts is insufficient to account for this activity in urine. However, it is likely that the intake of (228)Th was accompanied by similar activity of the parent (228)Ra, and biokinetic calculations show that decay of (228)Ra in vivo would produce sufficient (228)Th to account for the observed urine activity.

Adult↗

Some historical highlights and portents for the future of biomedical research on radium and the actinides.

Radiobiological research on the actinide elements has been a continuum since the first cryptic report by Hamilton at Berkeley, California, in February 1944. Yet certain landmarks in the work, certain people and certain organizations were responsible for the equivalent of quantum jumps in our concepts and understanding. This paper will review very briefly a few of these. Among them will be the realization of the biochemical and consequent biological differences between plutonium and radium, the first demonstration of carcinogenicity of the actinides, their behavior in bone, their relative toxicity, carcinogenesis after inhalation, the genesis of the "king-size" experiments to investigate their long-term effects, "hot particles" in lung, highlights of research with the transplutonics, and several others. To the extent possible, the review will consider not only the research findings, but their bearing on standard setting and the general operations in place at the time. Some of the past and current polemics will be touched upon.

Actinoid Series Elements↗

Cells at risk for the production of bone tumors in radium exposed individuals: an electron microscope study.

The endosteal cells of bone from a 75-yr-old woman who had acquired radium internally, as a consequence of her previous employment as a radium dial painter, are documented here for the first time by electron microscopy. As a result of amputation for a fibrosarcoma in the region of the right knee joint, fresh samples of bone and tumor tissue from the femur were made available. A sample of bone, also obtained at amputation from an unirradiated control patient, age 65, was examined from the same site in the femur. A comparison of the bone-marrow interface from the two patients showed that, unlike the control bone where cells were seen close to bone mineral a fibrotic layer was interposed between the marrow cells and the bone mineral in the bone from the radium case. This layer varied in thickness up to 50 microns and was often acellular, although cell remnants and cells, which appeared viable, were sometimes seen within this layer. It is suggested that irradiation of those cells proliferating within, and at the edge of, this replacement fibrotic layer may be the most important in the induction of bone tumors rather than the original cells lying within the 0-10 microns range from bone mineral which has previously been supposed. The nuclear dimensions of the endosteal bone lining cells and their distance from bone mineral have been measured in the bones from the radium and control cases. These dimensions are important not only in understanding the mechanisms by which bone tumors arise but in developing models of carcinogenic risks of other alpha-particle emitting isotopes such as plutonium.

Aged↗

A retention-excretion model for americium in humans.

This paper discusses current information on the biological behavior of americium and describes a biokinetic model for americium in humans. Emphasis is on the time-dependent distribution and excretion of systemic americium in the adult, but potential differences with age in parameter values are addressed, and predictive models of absorption of americium to blood from the respiratory and gastrointestinal (GI) tracts are provided in an appendix. The analysis builds on the author's previous biokinetic model for plutonium in humans and recent analyses and/or models of other authors regarding the behavior of americium and related elements in humans and laboratory animals. Compared with the retention model for americium implied in ICRP Publication No. 48, the present model, as applied to adults, yields reasonably similar whole-body retention of americium at all times, much less retention in the liver after a few months, somewhat greater retention in the total skeleton after a few years, and very similar long-term integrated activities of long-lived americium isotopes on bone surfaces. Compared with a previous model of Durbin and Schmidt, the present model, as applied to adults, predicts very similar retention in the liver at all times, somewhat smaller retention in the total skeleton after a few years, and somewhat greater urinary excretion rates at all times after acute uptake to blood.

Americium↗

Gross composition and plasma and extracellular water volumes of tissues of a reference mouse.

The laboratory mouse is a primary animal model for experimental radiation biology and pharmacology. The usefulness of the mouse for those purposes is enhanced if detailed data are available to define a Reference Mouse [weight and composition of soft tissues and bones and their in-life content of plasma and extracellular water (ECW)]. Only fragmentary data are available for wet weights and plasma volumes of soft tissues and bones of mice; there are no reports of total volume or distribution of ECW in mouse tissues. To remedy those defects, wet weight and composition of all major organs and soft tissues were measured, and measurements were made or estimates obtained for wet weights and composition of all bones of the young adult (12 to 13 wk old) female Swiss-Webster mouse. 125I-transferrin was used as a tracer for plasma, and 22Na was used as a tracer for ECW. Tissue weight and tracer measurements were conducted using the metabolic balance approach and a freezing technique that avoids blood loss during dissection. Results compare favorably with published weights and plasma volumes of tissues of mature mice of both genders and other strains. Total plasma volume (48.9 +/- 4.4 microL g-1) and Na-space (232 +/- 15 microL g-1), and the specific plasma and ECW volumes of vascular mouse tissues, exceed those of rat tissues. Applications of the data are presented: (1) interpretation of plutonium uptake kinetics in the mouse; (2) estimation of masses of mineralized bone tissue (1.92 g), bone marrow (1.2 g), and endosteal (BS) cells (0.2 g) of the mouse.

Animals↗

Inhalation doses for aboriginal people reoccupying former nuclear weapons testing ranges in South Australia.

The Australian Government plans to rehabilitate the former nuclear weapons testing ranges at Maralinga and Emu in South Australia and to allow access to the areas for the Pitjantjatjara (Aboriginal) people who are the traditional owners of the land. The major radiological hazard posed by reoccupation of the ranges arises from inhalation of residual plutonium. The committed effective dose that these people might receive from inhalation on reoccupation of the lands is computed for a range of sites. The estimated doses for permanent occupancy range up to 300 mSv y-1 indicating the need for substantial rehabilitation before these areas are suitable for unrestricted access.

Environmental Pollution↗

Radiocesium in the Savannah River Site environment.

The Savannah River Site has produced plutonium, tritium, and other special nuclear materials for national defense, other government programs, and some civilian purposes. Radiocesium, a waste product, has been released to the environment during the operation of five reactors, two radio-chemical processing facilities, and a high-level waste storage system. During the period 1955-1989, 130 GBq of 137Cs was released to the atmosphere and 2.2 x 10(4) GBq was released to site streams and ponds. Approximately 65% of the latter remained on the site. The maximum individual effective dose equivalent at the site boundary was estimated to be 3.3 microSv from atmospheric releases and 600 microSv from liquid releases. The 80-km population dose was 1.6 person-Sv.

Air Pollutants, Radioactive↗

Environmental monitoring in the vicinity of the Mayak atomic facility.

The goal of radiation monitoring in the zone influenced by the operation of the Mayak Production Association is to provide information for activities aimed at environmental preservation in that territory. The priority tasks of the radioecological monitoring system are measuring all parameters of radiation impact on the environment (which contribute up to 95% of the total population exposure dose), and estimating all parameters required to support effective decision-making. The basic methods for radioecological monitoring are: unification and standardization of field and laboratory techniques for radionuclide analysis; measurement of gamma-irradiation dose rate; measurement of 137Cs, 90Sr, and plutonium concentrations in soils; measurement of radionuclide concentration in surface and ground waters and the atmosphere; study of the pathways of horizontal and vertical migration of radionuclides in natural media; and establishment of data bases including ecological mapping. Based on the information obtained, assessment of contamination and forecasts of the future radiation situation are prepared using models.

Air Pollutants, Radioactive↗

An approach to dose reconstruction for the Urals population.

Population exposure in the Urals region occurred due to the releases of radionuclides by the Mayak plutonium facility in the 1950's. The major sources of radioactive contamination were the discharges of liquid wastes into the Techa river (1949-1956); an explosion in the storage facility for high level radioactive wastes which formed the East Urals Radioactive Trace in 1957; and gaseous aerosol releases within the first decade of the facility's operation (1949-1957). The problems of dose reconstruction for the population exposed on the Techa river banks and East Urals Radioactive Trace are outlined. The initial data sets and basic models for dose reconstruction are described. The main tasks of the Techa River Dosimetry System Project and the approaches to individual internal and external dose reassessment are formulated.

Humans↗

Estimation of the temporal distribution and dose dependency of lung cancers among workers of nuclear fuel reprocessing plants.

Lung cancer mortality among 4,279 workers at the Mayak nuclear complex who were exposed to chronic irradiation both externally and internally from incorporation of plutonium was analyzed in terms of a linear relative risk model. It is estimated that excess lung cancer risk is about 1.9 Sv(-1), with an average latent period of 24 y.

Dose-Response Relationship, Radiation↗

Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR.

This paper deals with our efforts to survey residual radioactivity in the soil sampled at the Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil was sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called "Bolapan," which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240Pu with weapons-grade plutonium were detected together with fission and activation products such as 137Cs, 60Co, 152Eu, and 154Eu.

Gamma Rays↗

Radionuclides in fishes and mussels from the Farallon Islands Nuclear Waste Dump Site, California.

The Farallon Islands Nuclear Waste Dump Site (FINWDS), approximately 30 miles west of San Francisco, California, received at least 500 TBq encapsulated in more than 47,500 containers from approximately 1945 to 1970. During several seasons in 1986/87 deep-sea bottom feeding fishes (Dover sole = Microstomus pacificus; sablefish = Anoplopoma fimbria; thornyheads = Sebastolobus spp.) and intertidal mussels (Mytilus californianus) were collected from the vicinity of the FINWDS and from comparable depths at a reference site near Point Arena, CA. Tissues were analyzed for several radionuclides (137Cs, 238Pu, 239+240Pu, and 241Am). Radionuclide concentrations for fish mussel tissue ranged from non-detectable to 4,340 mBq kg(-1) wet weight, with the following means for Farallon fishes: 137Cs = 1,110 mBq kg(-1); 238Pu = 390 mBq kg(-1); 239+240Pu = 130 mBq kg(-1); and 241Am = 1,350 mBq kg(-1). There were no statistically significant differences in the radionuclide concentrations observed in samples from the Farallon Islands compared to reference samples from Point Arena, CA. Concentrations of both 238Pu and 241Am in fish tissues (from both sites) were notably higher than those reported in literature from any other sites world-wide, including potentially contaminated sites. Concentrations of 239+24OPu from both sites were typical of low values found at some contaminated sites worldwide. These results show approximately 10 times higher concentrations of 239+240Pu and approximately 40-50 times higher concentrations of 238Pu than those values reported for identical fish species from 1977 collections at the FINWDS. Radionuclide concentrations were converted to a hypothetical per capita annual radionuclide intake for adults, yielding the following values of annual Committed Effective Dose Equivalent (CEDE) from ionizing radiation emitted from these radionuclides: 0.000 mSv y(-1) for 137Cs, 0.009 mSv Y(-1) for 228Pu, and 0.003 mSv y(-1) for 239+240Pu. For 241Am, projected CEDE for Dover sole, sablefish, and thornyheads were higher, averaging 0.03 mSv y(-1). The observed isotopic ratio of 238Pu/239+240Pu was about 4 (which is two orders of magnitude higher than the ratio of 0.03 associated with fallout from weapons tests and accidental releases in the north temperate zone of the earth), indicating a considerably higher environmental mobilization for 238Pu compared to 239+240Pu. Likewise, the observed ratio of 241Am/239+240Pu of about 30 was nearly two orders of magnitude higher than the fallout ratio of 0.43 in the north temperate zone of the earth. The projected ionizing radiation CEDE to people from the ingestion of fish with fallout radionuclides was three times higher for 241Am than from the plutonium isotopes.

Alpha Particles↗

A comprehensive appraisal of 241Am in soils around Rocky Flats, Colorado.

Soils east of Rocky Flats Plant (RFETS) near Golden, Colorado, were contaminated with actinides because of accidental release of oils laden with plutonium isotopes. Consequently, these soils were contaminated by 241Am due to radioactive decay of 241Pu (t1/2 = 14.4 y). A spatial analysis of 241Am activity in soils east of RFETS was conducted to elucidate the magnitude and the mode of 241Am dispersion in the soil environment. 241Am activity of 178 soil samples ranged from 0.037 Bq kg-1 to 10,004 Bq kg-1 with a mean of 214 Bq kg-1, median of 7.28 Bq kg-1, standard deviation of 942 Bq kg-1, and a coefficient of variation of 4.3. Spatial analysis of 241Am in soils around RFETS was conducted using indicator kriging, which is a nonparametric technique especially suitable to model a conditional cumulative distribution function (ccdf) of highly skewed environmental data such as 241Am. The ccdf was used to generate an E-type (mean of the conditional cdf) surface. The resulted surfaces were consistent with the hypothesis that the westerly winds were the dominant mechanism of americium dispersal. The spatial distribution and dispersal mechanisms of 241Am were similar to those of 239+240Pu. The ccdf was also used to construct probability of exceedence maps of 241Am in soils. For the purpose of this report two threshold values for the probability maps were selected: (1) the mean measured background activity of 241Am (0.4 Bq kg-1), and (2) the programmatic preliminary remediation goal for residential occupancy scenario (87.7 Bq kg-1). The probability-of-exceedance maps provide estimates of spatial uncertainty associated with each threshold. The E-type maps in conjunction with the probability-of-exceedance maps provide a robust framework for future cleanup options and land use decisions.

Americium↗

Dose assessment activities in the Republic of the Marshall Islands.

Dose assessments, both retrospective and prospective, comprise one important function of a radiological study commissioned by the Republic of the Marshall Islands (RMI) government in late 1989. Estimating past or future exposure requires the synthesis of information from historical data, results from a recently completed field monitoring program, laboratory measurements, and some experimental studies. Most of the activities in the RMI to date have emphasized a pragmatic rather than theoretical approach. In particular, most of the recent effort has been expended on conducting an independent radiological monitoring program to determine the degree of deposition and the geographical extent of weapons test fallout over the nation. Contamination levels on 70% of the land mass of the Marshall Islands were unknown prior to 1994. The environmental radioactivity data play an integral role in both retrospective and prospective assessments. One recent use of dose assessment has been to interpret environmental measurements of radioactivity into annual doses that might be expected at every atoll. A second use for dose assessment has been to determine compliance with a dose action level for the rehabilitation of Rongelap Island. Careful examination of exposure pathways relevant to the island lifestyle has been necessary to accommodate these purposes. Examples of specific issues studied include defining traditional island diets as well as current day variations, sources of drinking water, uses of tropical plants including those consumed for food and for medicinal purposes, the nature and microvariability of plutonium particles in the soil and unusual pathways of exposure, e.g., that which might be associated with cooking and washing outdoors and inadvertent soil ingestion. A study on the prevalence of thyroid disease is also being conducted and the geographic pattern of disease may be useful as a bioindicator of the geographic pattern of exposure to radioiodine. Finally, an examination is underway of gummed film, fixed-instrument, and aerial survey data accumulated during the 1950's by the Health and Safety Laboratory of the U.S. AEC. This article gives an overview of these many different activities and a summary of recent dose assessments.

Diet↗

Reconstruction of radionuclide releases from the Hanford Site, 1944-1972.

Historic releases of key radionuclides were estimated as a first step in determining the radiation doses that resulted from Hanford Site operations. The Hanford Site was built in southcentral Washington State during World War II to provide plutonium for the U.S. nuclear weapons program. As part of the Hanford Environmental Dose Reconstruction (HEDR) Project, releases to the Columbia River of 24Na, 32P, 46Sc, 51Cr, 56Mn, 65Zn, 72Ga, 76As, 90Y, 131I, 239Np, and nonvolatile gross beta activity from operation of eight Hanford single-pass production reactors were estimated. Releases of 90Sr, 103Ru, 106Ru, 131I, 144Ce, and 239Pu to the atmosphere from operation of chemical separation facilities were also estimated. These radionuclides and the atmospheric and Columbia River pathways were selected for study because scoping studies showed them to be the largest contributors to dose from Hanford operations. The highest doses resulted from releases to the atmosphere of 131I from chemical separations plants in the pre-1950 period. Prior to 1950, the technology for limiting iodine releases had not been developed. Hence, a very detailed reconstruction of the hourly 131I release history was achieved for 1944-1949 using Monte Carlo methods. Atmospheric releases of the other radionuclides were estimated on a monthly basis for 1944-1972 using deterministic calculations. Monthly releases to the Columbia River for 1944-1971 were based on Monte Carlo methods.

Air Pollutants, Radioactive↗

A comparison of independently conducted dose assessments to determine compliance and resettlement options for the people of Rongelap Atoll.

Rongelap Island was the home of Marshallese people numbering less than 120 in 1954; 67 were on the island and severely exposed to radioactive fallout from an atomic weapons test in March of that year. Those resident on Rongelap were evacuated 50 h after the test, returned 3 y later, then voluntarily left their home island in 1985 due to their ongoing fear of radiation exposure from residual radioactive contamination. Following international negotiations in 1991, a Memorandum of Understanding (MOU) was signed in early 1992 between the Republic of the Marshall Islands Government, the Rongelap Atoll Local Government, the U.S. Department of Energy, and the U.S. Department of the Interior. In this MOU it was agreed that the Republic of the Marshall Islands, with the aid of the U.S. Department of Energy, would carry out independent dose assessments for the purpose of assisting and advising the Rongelap community on radiological issues related to a safe resettlement of Rongelap. The MOU enacted two action levels which were agreed to be used to establish whether mitigation should be considered as a condition for resettlement of Rongelap Island: (1) no individual should receive an annual dose in the future of 1 mSv or more, above that from natural background radiation, assuming that his/her diet consists of only locally produced foods, and (2) the total surface soil concentration of plutonium and other transuranic elements must be less than 629 Bq kg(-1) (averaged over the top 5 cm). Environmental radiological data and dietary information were collected over two years (1992-1993) for the purpose of predicting future potential doses to Rongelapese who might resettle. In 1994, four independent assessments were reported, including one from each of the following entities: Marshall Islands Nationwide Radiological Study; Lawrence Livermore National Laboratory; an independent advisor from the United Kingdom (MCT); and a committee of the National Research Council. All four assessments concluded that possibly more than 25% of the adult population could exceed the 1 mSv y(-1) dose level based on strict utilization of a local food diet. The purpose of this report is to summarize the methodology, assumptions, and findings from each of four assessments; to summarize the recommendations related to mitigation and resettlement options; to discuss unique programmatic aspects of the study; and to consider the implications of the findings to the future of the Rongelap people.

Adult↗

Performance testing of the Eberline RMS-II criticality accident monitor.

The Plutonium Facility at Los Alamos uses Eberline RMS-II monitors as part of its criticality accident alarm system. The monitors are designed to accommodate a wide spectrum of criticality accident scenarios from both liquid and metal supercriticalities. A series of experiments were performed at the Los Alamos Critical Experiments Facility to evaluate the response of the monitor to a wide range of radiation transients. The primary objectives of the evaluation were to verify reliable and prompt latching of the criticality alarms in accordance with the performance criteria of ANSI/ANS-8.3-1986. The RMS-II monitor performed reliably during all of the experiments and was found to meet specific ANSI/ANS performance criteria for latching.

Evaluation Studies as Topic↗