Reconstructing historical trends of Berre lagoon contamination from surface sediment datasets: influences of industrial regulations and anthropogenic silt inputs.

These last decades, the Berre lagoon (in southeastern France) has been deeply affected since the 1930s by strong inputs of contaminants associated with industrial development and since 1966 by huge inputs of freshwater and silts due to the installation of a hydroelectric power plant. Surveys of the surface sediment contamination have been sparsely performed since 1964 for management and research purposes. These surveys were performed by various laboratories that investigated different chemicals and sampling areas using different analysis protocols. Therefore, the available data are disconnected in time and space and differ in quality. In order to reconstruct coherent time series of sediment contamination from this heterogeneous datasets and to discuss the influences of industrial and hydroelectric discharges we used a statistical approach. This approach is based on Principal Component Analysis (PCA) and Fuzzy clustering analysis on data from one extensive survey realized on surface sediments in 1976. The PCA allowed identifying two geochemical indexes describing the main surface sediment geochemical characteristics. The fuzzy clustering analysis on these indexes allowed identifying sub-areas under the specific influence of industrial or hydroelectric discharges. This allowed us to reconstruct, for each sub-area, a coherent and interpretable long-term time series of sediment contamination from the available database. Reconstructed temporal trends allowed us to estimate: (i) the overall decrease of sediment contamination since the mid-1970 attributed to industrial discharge regulations enacted at this period and (ii) the dilution of the concentrations of sediment bound contaminants induced by the hydroelectric power plant and its associated particulate matter inputs.

History, power, and electricity: American popular magazine accounts of electroconvulsive therapy, 1940-2005.

Electroconvulsive therapy (ECT) is a psychiatric treatment that has been in use in the United States since the 1940s. During the whole of its existence, it has been extensively discussed and debated within American popular magazines. While initial reports of the treatment highlighted its benefits to patients, accounts by the 1970s and 1980s were increasingly polarized. This article analyzes the popular accounts over time, particularly the ways in which the debates over ECT have revolved around different interpretations of ECT's history and its power dynamics.

A review of irradiated fuel particle releases from the Windscale Piles, 1950-1957.

Radiological assessments have assumed that the mass of irradiated uranium oxide particles inadvertently released to the atmosphere from the Windscale Piles, two nuclear reactors at Windscale Works, Sellafield, England, during the 1950s was 20 kg. This paper re-examines the assumptions upon which this figure was based and concludes that the value is a realistically conservative estimate of the release, consistent with current radiological protection practice. The mass estimate is derived from a reanalysis of plant data produced at the time. The environmental data on which the initial estimates were based are reconfirmed, and additional support is provided by an interpretation of modelling studies of both the total deposition and milk concentrations resulting from that deposition. Milk-monitoring data from the time are shown to be consistent with the release assumptions used in the dispersion modelling exercise. Finally, the issue of statistical undersampling is addressed using the particle numbers and size distributions produced by the modelling exercise.

A new compilation of the atmospheric 85krypton inventories from 1945 to 2000 and its evaluation in a global transport model.

This paper gives the yearly (85)Kr emissions of all known reprocessing facilities, which are the main sources of (85)Kr in the atmosphere since 1945, for the years 1945 until 2000. According to this inventory 10,600 PBq (Peta=10(15)) of (85)Kr have been globally emitted from the year 1945 until the end of 2000. The global atmospheric inventory at the end of the year 2000 amounts to 4800 PBq. These emissions have been incorporated into the ECHAM4 atmospheric general circulation model as point sources. Monthly mean model results are compared with measurements made at different locations and times. The influence of each source on the measured concentrations at various locations is studied. The calculated concentrations are found to give reasonably good agreement with the observations, indicating that the emission inventory is realistic. Although, at all northern hemispheric observation sites the model tends to slightly overestimate the concentrations. A possible reason for this overestimation can be found in model features (coarse resolution in time and space). The most prominent discrepancy that is consistently repeated at all northern hemispheric stations occurs in the early 1990s. This could most likely be related to an overestimate of sources. Possibly, the Russian emissions declined earlier than assumed in the current database. Another discrepancy between observations and simulations indicating an incompleteness of the release data is found at some southern hemispheric sites. The variability of their observations could only be explained by regional sources. However, several spikes occur after 1992 when no reprocessing facility is known to be in operation in the southern hemisphere. Production of isotopes for radiopharmaceuticals like technetium-99m from highly enriched uranium is the most likely explanation.

Power reactor health physics in the 1960s.

This note is a personal re-collection of some of the problems and experiences of the Health Physics Department staff at Dungeness Power Station during the period 1963-1971. This was a period of construction, commissioning, operating and learning. It was an interesting period for power reactor health physicists as appropriate instrumentation; information and experience were all in fairly short supply.

Regulation of nuclear radiation exposures in India.

India has a long-term program of wide spread applications of nuclear radiations and radioactive sources for peaceful applications in medicine, industry, agriculture and research and is already having several thousand places in the country where such sources are being routinely used. These places are mostly outside the Department of Atomic Energy (DAE) installations. DAE supplies such sources. The most important application of nuclear energy in DAE is in electricity generation through nuclear power plants. Fourteen such plants are operating and many new plants are at various stages of construction. In view of the above mentioned wide spread applications, Indian parliament through an Act, called Atomic Energy Act, 1964 created an autonomous body called Atomic Energy Regulatory Board (AERB) with comprehensive authority and powers. This Board issues codes, guides, manuals, etc., to regulate such installations so as to ensure safe use of such sources and personnel engaged in such installations and environment receives radiation exposures within the upper bounds prescribed by them. Periodic reports are submitted to AERB to demonstrate compliance of its directives. Health, Safety and Environment Group of Bhabha Atomic Research Centres, Mumbai carries out necessary surveillance and monitoring of all installations of the DAE on a routine basis and also periodic inspections of other installations using radiation sources. Some of the nuclear fuel cycle plants like nuclear power plants and fuel reprocessing involve large radioactive source inventories and have potential of accidental release of radioactivity into the environment, an Environmental Surveillance Laboratory (ESL) is set up at each such site much before the facility goes into operation. These ESL's collect baseline data and monitor the environment throughout the life of the facilities including the decommissioning stage. The data is provided to AERB and is available to members of the public. In addition, a multi-tier system of AERB permissions is in place to ensure that all aspects of safety have been considered before permission to operate is granted. The stages where permission of AERB is essential are site selection, design data, and several stages during construction and operation. The details required by AERB include provision for treatment and storage of radioactive waste, de-commissioning procedures and provision of costs. In addition to AERB, nuclear power plants have to comply with the requirements of Ministry of Environment and Forests and get their clearance. This is given on the basis of Environmental Impact Assessment Report which should satisfy the authorities that no ecological damage will be caused and the facility will not have adverse effect on the environment. In addition, the State Pollution Control Board where the facility is to be located has to permit the site of the plant for its proposed discharges into the environment. It is largely due to the above comprehensive regulatory controls that none of the plants in India had any accident during the last 34 decades of operation. The type of measurements carried out by the ESL's and results from a few typical ESL's will be presented.

Application of MARSSIM at the Big Rock Point Restoration Project.

Big Rock Point was Michigan's first commercial power reactor and operated for 35 years. It was permanently shut down in August of 1997, and the site is currently being returned to its natural state. Guidance contained in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) is being applied in preparation for the final status survey. Unlike other commercial power reactors currently undergoing decommissioning, all Big Rock Point structures will be removed prior to the final status survey. A historical site assessment along with characterization surveys formed the basis to designate 1.6 square kilometers (395.9 acres) of the site as non-impacted and the remaining 0.7 square kilometers (184.5 acres) as impacted as defined by MARSSIM. Also, a source term abstraction has been performed using historical waste stream data to identify radionuclides potentially present in site soils, hard-to-detect (HTD) radionuclides and surrogate radionuclides for the HTD radionuclides.

Japanese experiences of environmental management.

Japan experienced a very rapid industrialization and economic growth in the era of income doubling in 1960s and at the same time Japan experienced very severe damage from various types of environmental pollution. In this paper, historical development of population, GNP, energy consumption with classification of petroleum, coal and electric power, and CO2 emission are introduced as basic background data on Japanese development. The tragic experience of Minamata disease and Itai-itai disease caused by methyl mercury and cadmium, respectively, are introduced. In two tables, historical development of water pollution and air pollution are summarized. Regarding solid wastes management, the total mass balance in Japan and recent development in legislation framework for enhancement of recycling of wastes are introduced briefly.

Radiation litigation and the nuclear industry--the experience in the United Kingdom.

In the United Kingdom, the Nuclear Installations Act 1965 places a "strict" statutory duty on the operators of nuclear facilities to ensure that any exposure to radiation resulting from operations does not cause injury or damage. A claimant does not have to prove fault to receive compensation under the Act, only causation. The 1965 Act has been fundamental in shaping litigation involving the nuclear industry in the UK. Civil law cases brought under the Act will be heard before a single judge (with no jury or technical assessor) who must present his or her decision in a reasoned judgment. This process leads to a considerable volume of expert evidence being presented to the court and extensive cross-examination of witnesses. The expense and uncertain outcome of cases involving claims by nuclear workers that occupational exposure to radiation had caused the development of cancer has led to employers and trade unions setting up the voluntary Compensation Scheme for Radiation-linked Diseases as an alternative to litigation. This Scheme has worked well and is held up as a model of alternative dispute resolution. However, a few cases concerning personal injury or damage to property have come before the courts when the defendant nuclear operator considered that the claims were technically unjustified and where settlement was not a policy option. As anticipated, these cases were lengthy, complex, and expensive. The radiation doses assessed to have been received by the individuals who were the subject of claims, whether workers or members of the public, have been crucial to the outcome. The technical expertise of health physicists and allied specialists has been vital in establishing defensible estimates of dose, and this contribution can be expected to remain of high importance in radiation litigation in the UK.

[Health consequences of the Chernobyl accident]. / Helbredsmaessige konsekvenser af reaktorulykken i Tjernobyl.

The Chernobyl accident in 1986 has been and still is the subject of great interest. Journalistic reports often contain exaggerations and undocumented statements and much uncertainty about the true consequences of the accident prevails in the population. This article reviews the current literature with the focus on reports from official commissions and documentation in the form of controlled studies. The fatal deterministic consequences comprise about 30 victims. The most important outcome is a marked increase in the incidence of thyroid cancer in children and adolescents in the most heavily contaminated area. Furthermore, pronounced psychosocial problems are dominant in the population of the contaminated area. Other significant and documented health consequences are not seen.

Historical relationship between performance assessment for radioactive waste disposal and other types of risk assessment.

This article describes the evolution of the process for assessing the hazards of a geologic disposal system for radioactive waste and, similarly, nuclear power reactors, and the relationship of this process with other assessments of risk, particularly assessments of hazards from manufactured carcinogenic chemicals during use and disposal. This perspective reviews the common history of scientific concepts for risk assessment developed until the 1950s. Computational tools and techniques developed in the late 1950s and early 1960s to analyze the reliability of nuclear weapon delivery systems were adopted in the early 1970s for probabilistic risk assessment of nuclear power reactors, a technology for which behavior was unknown. In turn, these analyses became an important foundation for performance assessment of nuclear waste disposal in the late 1970s. The evaluation of risk to human health and the environment from chemical hazards is built on methods for assessing the dose response of radionuclides in the 1950s. Despite a shared background, however, societal events, often in the form of legislation, have affected the development path for risk assessment for human health, producing dissimilarities between these risk assessments and those for nuclear facilities. An important difference is the regulator's interest in accounting for uncertainty.

Discharges of krypton from Sellafield, 1951-1997, and the resultant doses to members of the public.

The radionulide 85Kr, which has a half-life of 10.72 years, is produced, almost exclusively, by reprocessing operations during which the fission product is released from irradiated nuclear fuel by chemical dissolution. Reprocessing plants at Sellafield, in Cumbria, have released the noble gas to atmosphere since operations commenced in 1952. Historically, krypton discharges were classified for security reasons, although these have been monitored and published by BNFL for each year since 1977. This paper reviews discharges of 85Kr from Sellafield, and consequent radiation doses, since its earliest operations. Over the past three years, discharges of 85Kr have increased due to the operation of the Thermal Oxide Fuel Reprocessing Plant (Thorp). Nonetheless, the associated annual committed effective dose to individuals remains low, peaking around 1.5 microSv a-1 to the identified critical groups, which compares with typical annual committed effective doses from natural sources of radiation of 2200 microSv. Maximum collective doses predicted from any single year of operations are 0.6 man Sv, 2 man Sv and 42 man Sv to the UK, Europe and the world respectively. Comparison may be made to natural background committed effective doses, which are of the order of 130,000 man Sva-1, 750,000 man Sva-1 and 13,000,000 man Sva-1 to the UK, EU and world populations respectively.