Radionuclides Of Concern Research Articles

Uranium decay daughters from isolated mines: Accumulation and sources

This study combines in situ gamma spectrometry performed at different scales, in order to accurately locate the contamination pools, to identify the concerned radionuclides and to determine the distribution of the contaminants from soil to bearing phase scale. The potential mobility of several radionuclides is also evaluated using sequential extraction. Using this procedure, an accumulation area located downstream of a former French uranium mine and concentrating a significant fraction of radioactivity is highlighted. We report disequilibria in the U-decay chains, which are likely related to the processes implemented on the mining area. Coupling of mineralogical analyzes with sequential extraction allow us to highlight the presence of barium sulfate, which may be the carrier of the Ra-226 activities found in the residual phase (Ba(Ra)SO4). In contrast, uranium is essentially in the reducible fraction and potentially trapped in clay-iron coatings located on the surface of minerals.

Development of the Plutonium-DTPA Biokinetic Model.

Estimating radionuclide intakes from bioassays following chelation treatment presents a challenge to the dosimetrist due to the observed excretion enhancement of the particular radionuclide of concern where no standard biokinetic model exists. This document provides a Pu-DTPA biokinetic model that may be used for making such determination for plutonium intakes. The Pu-DTPA biokinetic model is intended to supplement the standard recommended biokinetic models. The model was used to evaluate several chelation strategies that resulted in providing recommendations for effective treatment. These recommendations supported early treatment for soluble particle inhalations and an initial 3-day series of DTPA treatments for wounds. Several late chelation strategies were also compared where reduced treatment frequencies proved to be as effective as multiple treatments. The Pu-DTPA biokinetic model can be used to assist in estimating initial intakes of transuranic radionuclides and for studying the effects of different treatment strategies.

Construction of a naturally occurring radioactive material project in the BeAAT hazardous waste facilities.

This paper does not necessarily reflect the views of the International Commission on Radiological Protection. Naturally occurring radioactive material (NORM) is produced during exploration and production operations of subsidiaries of the Abu Dhabi National Oil Company (ADNOC) in the United Arab Emirates, and accumulates in drilling tubulars, plant equipment, and components. These NORM hazardous wastes need to be managed in such a way that they do not damage human health and the environment. The primary radionuclides of concern in the oil and gas industries are radium-226 and radium-228. These radioisotopes are the decay products of uranium and thorium isotopes that are present in subsurface formations from which hydrocarbons are produced. While uranium and thorium are largely immobile, radium is slightly more soluble and may become mobilised in the fluid phases of the formation (International Association of Oil & Gas Producers, 2008). In order to treat and dispose of NORM waste products safely, ADNOC's subsidiary 'TAKREER' is developing a new facility, on behalf of all ADNOC subsidiaries, within the existing Central Environmental Protection Facilities (BeAAT) in Ruwais city. The NORM plant is envisaged to treat, handle, and dispose of NORM waste in the forms of scale, sludge, and contaminated equipment. The NORM treatment facility will cover activities such as decontamination, volume reduction, NORM handling, and concrete immobilisation of NORM waste into packages for designated landfilling.

Gene expression response of mice after a single dose of 137CS as an internal emitter.

Cesium-137 is a radionuclide of concern in fallout from reactor accidents or nuclear detonations. When ingested or inhaled, it can expose the entire body for an extended period of time, potentially contributing to serious health consequences ranging from acute radiation syndrome to increased cancer risks. To identify changes in gene expression that may be informative for detecting such exposure, and to begin examining the molecular responses involved, we have profiled global gene expression in blood of male C57BL/6 mice injected with 137CsCl. We extracted RNA from the blood of control or 137CsCl-injected mice at 2, 3, 5, 20 or 30 days after exposure. Gene expression was measured using Agilent Whole Mouse Genome Microarrays, and the data was analyzed using BRB-ArrayTools. Between 466-6,213 genes were differentially expressed, depending on the time after 137Cs administration. At early times (2-3 days), the majority of responsive genes were expressed above control levels, while at later times (20-30 days) most responding genes were expressed below control levels. Numerous genes were overexpressed by day 2 or 3, and then underexpressed by day 20 or 30, including many Tp53-regulated genes. The same pattern was seen among significantly enriched gene ontology categories, including those related to nucleotide binding, protein localization and modification, actin and the cytoskeleton, and in the integrin signaling canonical pathway. We compared the expression of several genes three days after 137CsCl injection and three days after an acute external gamma-ray exposure, and found that the internal exposure appeared to produce a more sustained response. Many common radiation-responsive genes are altered by internally administered 137Cs, but the gene expression pattern resulting from continued irradiation at a decreasing dose rate is extremely complex, and appears to involve a late reversal of much of the initial response.

Estimation of radionuclide transport to reactor containment building under unprotected severe accident scenario in SFR

In the design of Sodium cooled Fast Reactor (SFR), Defense in Depth (DiD) approach is followed with multiple barriers to limit the release of radionuclides to the environment under accidental conditions. Under severe accident scenario, the multiple barriers provided as part of DiD, can fail one by one and finally the radionuclides may be released to Reactor Containment Building (RCB). Under severe accident scenario, the extent of radionuclides release into the environment has to be limited based on the permissible dose to the public at the site exclusion zone boundary. The radionuclides of concern for SFR under accidental release are noble gases and volatile fission products (Cs, I, Te). A lumped analytical methodology has been developed to estimate the source term in the core and transport of radionuclides to cover gas region/RCB under severe accident scenario in SFR. The methodology estimates the fission product inventory in the core based on saturation analysis method. In the event of severe accident, the core melts and fission products are released into the sodium pool. The transport of fission products (volatile and non-volatile) from pool to cover gas region/RCB takes place mainly by the short term phenomenon (noble gas bubble transport) and sodium spray fire release. The transport of Volatile Fission Products (VFPs) to cover gas region/RCB also takes place via the long term phenomenon (by evaporation). The evaporative transport of VFPs from hot pool to cover gas region is evaluated based on equilibrium partition coefficient (KD). The methodology is verified with the results for radionuclide inventory in SFR core, available in literature and their fractional release to the RCB. This methodology is useful for the evaluation of public dose at the site exclusion zone boundary of a typical SFR under severe accident scenario.

Measurement of radioactivity levels and assessment of radioactivity hazards of soil samples in Karaman, Turkey

In this study, the levels of the natural and artificial radioactivity in soil samples collected from surrounding of Karaman in Turkey were measured. Activity concentrations of the concerned radionuclides were determined by gamma-ray spectrometry using a high-purity germanium detector with a relative efficiency of 40 % at 1.332 MeV. The results obtained for the (238)U series ((226)Ra, (214)Pb and (214)Bi), (232)Th series ((228)Ac), (40)K and fission product (137)Cs are discussed. To evaluate the radiological hazard of radioactivity in samples, the radium equivalent activity (Raeq), the absorbed dose rate (D), the annual effective dose and the external (Hex) and internal hazard index (Hin) were calculated and presented in comparison with the data collected from different areas in the world and Turkey.

Determination and Maintenance of de Minimis Risk for Migration of Residual Tritium (3H) From the 1969 Project Rulison Nuclear Test to Nearby Hydraulically Fractured Natural Gas Wells

The Project Rulison underground nuclear test was a proof-of-concept experiment that was conducted under the Plowshare Program in 1969 in the Williams Fork Formation of the Piceance Basin in west-central Colorado. Today, commercial production of natural gas is possible from low permeability, natural gas bearing formations like that of the Williams Fork Formation using modern hydraulic fracturing techniques. With natural gas exploration and production active in the Project Rulison area, this human health risk assessment was performed in order to add a human health perspective for site stewardship. Tritium (H) is the radionuclide of concern with respect to potential induced migration from the test cavity leading to subsequent exposure during gas-flaring activities. This analysis assumes gas flaring would occur for up to 30 d and produce atmospheric H activity concentrations either as low as 2.2 × 10 Bq m (6 × 10 pCi m) from the minimum detectable activity concentration in produced water or as high as 20.7 Bq m (560 pCi m), which equals the highest atmospheric measurement reported during gas-flaring operations conducted at the time of Project Rulison. The lifetime morbidity (fatal and nonfatal) cancer risks calculated for adults (residents and workers) and children (residents) from inhalation and dermal exposures to such activity concentrations are all below 1 × 10 and considered de minimis. The implications for monitoring production water for conforming health-protective, risk-based action levels also are examined.

Radionuclide activity concentrations in forest surface fuels at the Savannah River Site

Background/objectiveA study was undertaken at the United States Department of Energy's Savannah River Site (SRS), Aiken, South Carolina to investigate radionuclide activity concentrations in litter and duff from select areas at SRS. Litter (i.e. vegetative debris) and duff (i.e. highly decomposed vegetative debris) can often be the major fuels consumed during prescribed burns and have potential to release radiological contaminants into the environment. MethodsRepeated samples from 97 locations were collected systematically across SRS and analyzed for radionuclide activity. Radionuclide activity concentrations found in litter and duff were compared. As spatial trends were of interest, spatial distributions of radionuclide activity concentrations found in litter and duff and spatial dependency amongst the data were explored. Results7Be, 40K, and 137Cs showed statistically significant proportional differences between litter and duff samples. Duff sample concentrations for 137Cs (p < 0.0001) and 40K (p = 0.0015) were statistically higher compared to litter samples. 7Be activity concentrations were statistically higher in litter as compared to duff (p < 0.0001). For 40K litter and duff samples, spatial correlation tests were not significant at p = 0.05 and the maps did not indicate any apparent high concentrations centered near possible radionuclide sources (i.e. SRS facilities). For 7Be litter samples, significant spatial correlation was calculated (p = 0.0085). No spatial correlation was evident in the 7Be duff samples (p = 1.0000) probably due to small sample size (n = 7). 137Cs litter and duff samples showed significant spatial correlations (p < 0.0001 and p < 0.0001, respectively). ConclusionsTo date, few studies characterize radionuclide activity concentrations in litter and duff, and to our knowledge none present spatial analysis. Key findings show that across SRS, 137Cs is the primary radionuclide of concern, with the highest number of samples reported above MDC in litter (51.4%) and duff samples (83.2%). However, 137Cs litter and duff spatial trends in the maps generated from the kriging parameters do not appear to directly link the areas with higher activity concentrations with SRS facilities. The results found herein provide valuable baseline monitoring data for future studies of forest surface fuels and can be used to evaluate changes in radioactivity in surface fuels in the southeast region of the U.S.

INVESTIGATION OF MAGNETIC NANOPARTICLES FOR THE RAPID EXTRACTION AND ASSAY OF ALPHA-EMITTING RADIONUCLIDES FROM URINE: DEMONSTRATION OF A NOVEL RADIOBIOASSAY METHOD

In the event of an accidental or intentional release of radionuclides into a populated area, massive numbers of people may require radiobioassay screening as triage for dose-reduction therapy or identification for longer-term follow-up. If the event released significant levels of beta- or alpha-emitting radionuclides, in vivo assays would be ineffective. Therefore, highly efficient and rapid analytical methods for radionuclide detection from submitted spot urine samples (≤50 mL) would be required. At present, the quantitative determination of alpha-emitting radionuclides from urine samples is highly labor intensive and requires significant time to prepare and analyze samples. Sorbent materials that provide effective collection and enable rapid assay could significantly streamline the radioanalytical process. The authors have demonstrated the use of magnetic nanoparticles as a novel method of extracting media for four alpha-emitting radionuclides of concern (polonium, radium, uranium and americium) from chemically-unmodified and pH-2 human urine. Herein, the initial experimental sorption results are presented along with a novel method that uses magnetic nanoparticles to extract radionuclides from unmodified human urine and then collect the magnetic field-induced particles for subsequent alpha-counting-source preparation. Additionally, a versatile human dose model is constructed that determines the detector count times required to estimate dose at specific protective-action thresholds. The model provides a means to assess a method's detection capabilities and uses fundamental health physics parameters and actual experimental data as core variables. The modeling shows that, with effective sorbent materials, rapid screening for alpha-emitters is possible with a 50-mL urine sample collected within 1 wk of exposure/intake.

Treatment of 106Ru Present In Intermediate Level Radioactive Liquid Waste With Nickel Sulphide

106Ru is one of the major radionuclides of concern in the aqueous radioactive waste generated during the reprocessing of the spent fuel. Intermediate level radioactive liquid waste (ILW) stream is generated during reprocessing of spent fuel and is neutralised with alkali to enable it to be stored in carbon steel tank. The waste is initially treated for 137Cs recovery using a specific resorcinol formaldehyde (RF) ion exchange resin. The effluent stream from the ion exchange treatment process has significant activity due to 106Ru. The present paper deals with a chemical treatment study for removal of 106Ru in the effluent using sulphides of cobalt and nickel. The decontamination factor of 250 obtained using NiS (at 2500 ppm concentration of Ni2+) is distinctly better than that obtained using CoS (at 7200 ppm concentration of Co2+).

Distribution of radiocesium and natural gamma emitters in pine needles in coniferious forest sites of Izmir

Using a high-resolution gamma-spectrometer system, the activity concentrations of 7Be, 137Cs, 40K and 226Ra were determined in the pine needles. Activity concentrations of the concerned radionuclides in the needle samples were as follows: 7Be, 24.6±2.40 to 210±7.21 Bq kg −1, 40K, 23.5±12.4 to 287±15.6 Bq kg −1, 226Ra, 0.44±0.12 to 12.3±2.18 Bq kg −1, and 137Cs, 0.61±0.30 to 2.29±0.38 Bq kg −1. It is found that the frequency distributions obtained for 7Be and 137Cs can be fitted to a normal distribution, and for 40K and 226Ra can be fitted to a log-normal distribution.

Determination of Technetium and Its Speciation by Surface-Enhanced Raman Spectroscopy

Technetium-99 (Tc) is an important radionuclide of concern, and there is a great need for its detection and speciation analysis in the environment. For the first time, we report that surface-enhanced Raman spectroscopy (SERS) is capable of detecting an inorganic radioactive anion, pertechnetate (TcO4-), at approximately 10(-7) M concentration levels. The technique also allows the detection of various species of Tc such as oxidized Tc(VII) and reduced and possibly complexed Tc(IV) species by use of gold nanoparticles as a SERS substrate. The primary Raman scattering band of Tc(VII) occurs at about 904 cm-1, whereas reduced Tc(IV) and its humic and ethylenediaminetetraacetic acid (EDTA) complexes show scattering bands at about 866 and 870 cm-1, respectively. Results also indicate that Tc(IV)-humic complexes are unstable and reoxidize to TcO4- upon exposure to oxygen. This study demonstrates that SERS could potentially offer a new tool and opportunity in studying Tc and its speciation and interactions in the environment at low concentrations.

Naturally occurring radioactive materials in cargo at US borders

In the USA and other countries large numbers of vehicles pass through border crossings each day. The illicit movement of radioactive sources is a concern that has resulted in the installation of radiation detection and identification instruments at border crossing points. This activity is judged to be necessary because of the possibility of an act of terrorism involving a radioactive source that may include any number of dangerous radionuclides. The problem of detecting, identifying and interdicting illicit radioactive sources is complicated by the fact that many materials present in cargo are somewhat radioactive. Some cargo contains naturally occurring radioactive material that may trigger radiation portal monitor alarms. Such nuisance alarms can be an operational limiting factor for screening of cargo at border crossings. Information about the nature of the radioactive materials in cargo that can interfere with the detection of radionuclides of concern is necessary to help anticipate and recognise likely sources of these nuisance alarms.

Measurement of terrestrial radiation for assessment of gamma dose from cultivated and barren saline soils of Faisalabad in Pakistan

Natural radioactivity originates from extraterrestrial sources as well as from primordial radioactive elements in the earth crust. The amount of radioactivity in soil varies widely and is a source of continuous exposure of human beings to terrestrial radioactivity that depends upon the type of soil and its uses. For the investigation of radioactivity in barren and cultivated soil, an area of about 80 ha of saline soil was selected in Pakka Anna near the city of Faisalabad in the Punjab province of Pakistan. Activity concentration levels due to 40K, 137Cs, 226Ra and 232Th were measured with HPGe detector in 250 saline soil samples collected at a spacing of about 8 ha at a depth of 0–25 cm with intervals of 5 cm depth. Activity concentration ranges of the concerned radionuclides for both of the soils were as follows: 40K, for barren and cultivated saline soil was 499–604 and 563– 629 Bq kg - 1 , respectively; 137Cs, 3.57–3.63 and 1.98– 5.15 Bq kg - 1 ; 226Ra, 24–29 and 27– 33 Bq kg - 1 , and 232Th, 49–54 and 46– 62 Bq kg - 1 . Gamma dose was estimated using the activity to dose rate conversion factors. The measured activity concentrations and the estimated radiation dose were found to be lying within the range specified in the 2000 report of UNSCEAR. Chemical analysis for Na, Ca and Mg was also carried out along with the measurement of electrical conductivity and pH of soil samples.

Natural environmental radioactivity and estimation of radiation exposure from saline soils

The study was conducted for the investigation of amount of radioactivity in the barren and cultivated soil of Bio saline Research Station in Pakka Anna, established by Nuclear Institute for Agriculture and Biology (NIAB) in 1990, 34 km. away from the city of Faisalabad, in the Punjab province of Pakistan. The studies were done on an area of about 100 hectares of two types of virgin and fertilized saline soils. The technique of gamma ray spectrometry was applied using HPGe (high purity germanium) gamma ray detector and a PC based MCA. Activity concentration levels due to 40 K, 137 Cs, 226 Ra and 232 Th were measured in 250 saline soil samples collected at a spacing of about 4 hectares at the depth level of 0–25 cm. with a step of 5 cm. depth. Activity concentrations ranges of the concerned radionuclides for both of the soils were as follows: 40 K, for virgin and cultivated saline soil was 500−610.2 and Bq/kg 560.2−635.6 respectively; 137 Cs, 3.57−3.63 and 1.98−5.15 Bq/kg 238 U, 26.3−31.6 and 30.3−38.7 Bq/kg, and 232 Th, 50.6−55.3 and 50.6−64.0 Bq/kg respectively. The absorbed dose rate in air lies in the region 63-73 nGyh -1 and 68-83 nGyh -1 for virgin and fertilized soils respectively. This indicates that this region lies in the area of higher radiation background, while comparing with the worlds’ average. The slightly higher value of dose in the fertilized farm may be due to the use of fertilizers for cultivation. Before the radiometric measurements, chemical analysis for concentration of Na, Ca and Mg was also carried out along with the measurement of electrical conductivity and pH of the soil samples.

Measurement of environmental radioactivity for estimation of radiation exposure from saline soil of Lahore, Pakistan

Radioactivity, natural and man made, is omnipresent in the earth's crust in different amounts. The soil on the earth's crust is a source of continuous exposure to human beings. The amount of radioactivity in soil depends upon the type of soil and its uses. The soil of barren area should show different amount of radioactivity when compared with that of the cultivated soil. For the investigation of amount of radioactivity in the barren soil, an area of about 60 h of saline soil was selected in Rakh Dera Chal near the city of Lahore in the Punjab province of Pakistan. The technique of gamma ray spectrometry was applied using high purity germanium gamma-ray detector and a PC based MCA. Activity concentration levels due to 40 K, 137 Cs, 226 Ra and 232 Th were measured in 125 saline soil samples collected at a spacing of about 4 ha at the depth level of 0– 25 cm with a step of 5 cm depth. Activity concentrations of the concerned radionuclides were as follows: 40 K , 524.84– 601.62 Bq kg −1 , 137 Cs , not detected (less than the lower detection limit), 226 Ra , 24.73– 28.17 Bq kg −1 , and 232 Th , 45.46– 52.61 Bq kg −1 . Before the radiometric measurements, chemical analysis for concentration of Na, Ca and Mg was also carried out along with the measurement of electrical conductivity and Ph of soil samples.

Évaluation de la toxicité chimique des radionucléides à vie longue sur la base des directives de qualité pour l'eau de boisson fixées par l'OMS

Assessment of the chemical toxicity of long-lived radionuclides on the hasis of WHO guidelines for drinking-water quaiity. The current assessment of health risks related to long lived radionuclides waste management is not complete if accounting only for radiological toxicity aspects. Although such an approach is justified for a large number of radionuclides of concern, it nevertheless cannot be exclusive and generalised: the chemical toxicity should be considered for radionuclides with a radioactive haif-Me exceeding id years. When assessing the chemical or radiological toxicity of a radionuclide, a reference dose applicated to drinking water consumption (0.1 mSv/year) can be compared to existing toxicologid data. Such an approach has been used by the World Heaith Organization for natural uranium, for which a guideline value in drinking water derived from its chemical toxicity (2 @) is recommended. WHO'S approach is used here for illustrating that the potential chemical toxicity of an element is to be considered for assessing health risks related to long-lived radionuclides.

Dose Assessment Associated with Landspreading of Petroleum-Industry Naturally Occuring Radioactive Material

As a result of oil and gas production and processing operations, naturally occurring radioactive material (NORM) sometimes accumulates at elevated concentrations in byproduct waste streams. The primary radionuclide of concern in NORM wastes are radium-226 (Ra-226) of the uranium-238 decay series; radium-228 of the thorium-232 decay series is also present, but usually at lower concentrations. The production waste streams most likely to be contaminated by elevated radium concentrations include produced water, scale, and sludge. Scales and sludges removed from production equipment sometimes are disposed of by landspreading, a method in which wastes are spread over the soil surface to allow the hydrocarbon component of the wastes to degrade. The disposal of NORM-contaminated wastes by landspreading was modeled to evaluate potential radiological doses to the general public. A variety of future land use scenarios—including residential, industrial, recreational, and agricultural scenarios—were considered. The waste streams considered included scales and sludges containing NORM above background levels. The RESRAD computer code was used to estimate the radiological doses for the maximally exposed receptor for each scenario. Depending on the land-use scenario, potential exposure pathways evaluated for the general public included external radiation; inhalation of contaminated particulates; inhalation of indoor and outdoor radon-222; inadvertent ingestion of contaminated soil; and ingestion of crops, milk, and meat grown on the property. Potential doses were modeled for a unit concentration of 1Bqg-1 of Ra-226 in soil. Because dose increases linearly with radium concentration, doses were extrapolated for a range of radium concentrations.

Public involvement in science and decision making.

Members of the public are becoming increasingly interested in understanding risks associated with their exposure to radionuclides and chemicals in the environment. They also want to be more involved in decision making about future exposures to risks. This paper reviews one community's involvement in decisions about technical methods to calculate soil cleanup criteria for the Rocky Flats Environmental Technology Site near Denver, Colorado. The public anticipated that much of the site would be available for their use following cleanup. Final decisions regarding the future use of the site have yet to be made; however, the soil action levels were developed for this eventuality. When the public expressed considerable concern about cleanup standards for the site in 1996, a community group met to focus efforts on reviewing the cleanup standards. Later, the U.S. Department of Energy officially established the community panel to oversee an independent calculation of radionuclide soil action levels that would be used as the basis for cleanup at Rocky Flats. The primary radionuclide of concern was 239+240Pu. The Radionuclide Soil Action Level Oversight Panel (Panel) was substantively involved in all aspects of the work, from selecting the contractor, approving the computer code that formed the basis of the calculation, and assisting in developing the exposure scenarios, to selecting the values for the numerous input parameters. Communicating the uncertainties to the public, which was a major component of the analysis of soil action levels, presented a unique challenge. Over the course of the 18-mo project, the Panel and interested members of the public gained an understanding of the technical elements of the calculation and the sensitivities of the different parameters. This project serves as an excellent model of the effectiveness of public involvement in science and decision making for the future. It also illustrates the public expectations, difficulties, and time commitments encountered when making scientific decisions in a public forum. Although the process was time consuming for the scientists responsible for the calculations, a more technically defensible as well as publicly acceptable soil action level emerged. The technical approach developed during the project has been recommended for use as a decision-making tool for cleanup of the site.

The radiochemist's role in the quality evaluation and assessment of radiological data in environmental decision making.

The quality evaluation and assessment of radiological data is the final step in the overall environmental data decisionprocess. This quality evaluation and assessment process is performed outside of the laboratory, and generally the radiochemist is not involved. However, with the laboratory quality management systems in place today, the data packages of radiochemical analyses are frequently much more complex than the project/program manager can effectively handle and additionally, with little involvement from radiochemists in this process, the potential for misinterpretation of radiological data is increasing. The quality evaluation and assessment of radiochemistry data consists of making three decisions for each sample and result, remembering that the laboratory reports all the data for each analyses as well as the uncertainty in each of these analyses. Therefore, at the data evaluation and assessment stage, the decisions are: (1) is the radionuclide of concern detected (each data point always has a number associated with it?); (2) is the uncertainty associated with the result greater than would normally be expected; and (3) if the laboratory rejected the analyses is there serious consequences to other samples in the same group? The need for the radiochemist's expertise for this process is clear. Quality evaluation and assessment requires the input of the radiochemist particularly in radiochemistry because of the lack of redundancy in the analytical data. This paper describes the role of the radiochemist in the quality assessment of radiochemical data for environmental decision making.