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This interlaboratory comparison was conducted to evaluate the performance of the Latin-American Biodosimetry Network (LBDNet) in analyzing digitized images for scoring dicentric chromosomes from in vitro irradiated blood samples. The exercise also assessed the use of weighted robust algorithms to compensate the uneven expertise among the participating laboratories. Three sets of coded images obtained through the dicentric chromosome assay from blood samples irradiated at 1.5 Gy (sample A) and 4 Gy (sample B), as well as a non-irradiated whole blood sample (sample C), were shared among LBDNet laboratories. The images were captured using the Metafer4 platform coupled with the AutoCapt module. The laboratories were requested to perform triage scoring, conventional scoring, and dose estimation. The dose estimation was carried out using either their laboratory calibration curve or a common calibration curve. A comparative statistical analysis was conducted using a weighted robust Hampel algorithm and z score to compensate for uneven expertise in dicentric analysis and dose assessment among all laboratories. Out of twelve laboratories, one had unsatisfactory estimated doses at 0 Gy, and two had unsatisfactory estimated doses at 1.5 Gy when using their own calibration curve and triage scoring mode. However, all doses were satisfactory at 4 Gy. Six laboratories had estimated doses within 95% uncertainty limits at 0 Gy, seven at 1.5 Gy, and four at 4 Gy. While the mean dose for sample C was significantly biased using robust algorithms, applying weights to compensate for the laboratory's analysis expertise reduced the bias by half. The bias from delivered doses was only notable for sample C. Using the common calibration curve for dose estimation reduced the standard deviation (s*) estimated by robust methods for all three samples. The results underscore the significance of performing interlaboratory comparison exercises that involve digitized and electronically transmitted images, even when analyzing non-irradiated samples. In situations where the participating laboratories possess different levels of proficiency, it may prove essential to employ weighted robust algorithms to achieve precise outcomes. [ABSTRACT FROM AUTHOR]

In radiochemical analysis of decommissioning waste, reference materials are not commercially available and consequently intercomparison exercises are needed for method validations. This paper reports the results from an intercomparison exercise focusing on analyses of α-emitter radionuclides in spent ion exchange resin. The exercise and statistical analysis of the submitted results were carried out based on ISO 13528 standard according to which the assigned values were calculated from the participant's results and the performances were assessed using z-scores, which showed excellent performance for all 241Am analyses, good performance for 238Pu analyses, tolerable performance for 239,240Pu analyses, and questionable 243,244Cm analyses. [ABSTRACT FROM AUTHOR]

Characterisation of activated reactor components is a multifaceted effort, which include both experimental work and activation calculations which together form a comprehensive characterisation approach. However, both the experimental work and activation calculations have their constraints and uncertainties. This work presents the characterisation of a highly activated stainless steel pipe including sampling planning, sampling, sub-sampling, elemental and radionuclide analyses, and activation calculations. 55Fe, 63Ni and 60Co analyses were carried out in a trilateral intercomparison exercise and the results were compared with activation calculations. The results showed excellent alignment between experimental and activation calculation results. [ABSTRACT FROM AUTHOR]

A need for method validation in radiochemical analyses of decommissioning waste is a challenging task due to lack of commercial reference materials. Participation in an intercomparison exercise is one way for a laboratory to assess their performance and validate their analysis results. A three-year project within the Nordic Nuclear Safety Research (NKS) community was initiated in order to carry out intercomparison exercises on difficult to measure (DTM) radionuclides in real decommissioning waste. Both Nordic and Non-Nordic laboratories participated. This paper reports the results from the final year of the project focusing on beta- and gamma emitter (i.e., easy to measure, ETM) analysis in spent ion exchange resin. The assigned values were derived from the participants' results according to ISO 13528 standard and the performances were assessed using z scores. The results showed generally good performances for both DTMs and ETMs. [ABSTRACT FROM AUTHOR]

The complex behavior of tritium and the probability of increasing tritium concentrations released in the environment were the promotors for the research and development of laboratory methods that enable to accurately determine the various forms of tritium including organically-bound tritium (OBT) for public and regulatory assurance. The measurement of tritium is a key step for dose and risk assessment. The Cernavoda Nuclear Power Plant (NPP) in Romania improved preparation methods and tested environmental matrices for OBT analysis through intercomparison exercises. This paper describes the international Organically-Bound Tritium (OBT) intercomparison exercise, organized by the Cernavoda Nuclear Power Plant (NPP) in 2019–2020, using fruit sample (quince) from Cernavoda town. Evaluation of the results from the participating laboratories was performed using both robust analysis (Algorithm A) method described in the ISO 13528:2015 standard and ANOVA method. The results obtained are encouraging as an increased number of participating laboratories did not change the observed dispersion of the results for activity concentration level around 50 Bq/L of combustion water. The stability of the remaining sample will be checked in time to investigate its use as a reference material for OBT analysis at the environmental levels. • The paper details the international intercomparison exercise for Organically-Bound Tritium (OBT), conducted by the Cernavoda Nuclear Power Plant (NPP) during 2019–2020, utilizing a quince fruit sample from the town of Cernavoda. • The results from the participating laboratories were evaluated in collaboration with colleagues from CEA/IBFJ/IRCM/SREIT/LRT in France, utilizing both the robust analysis (Algorithm A) method outlined in the ISO 13528:2015 standard and the ANOVA method. • The outcomes of the 6th OBT intercomparison exercise, which utilized quince samples, are promising. A significant number of participating laboratories maintained the observed dispersion of results for the activity concentration level at approximately 50 Bq/L of combustion water. • Additional tests will be conducted on the remaining sample to assess the temporal stability of the matrix during the development of a reference material for organically bound tritium (OBT) analysis at environmental levels. • The discussions and publication of results for this study have been delayed due to the pandemic, which has impacted research activities in numerous laboratories worldwide. [ABSTRACT FROM AUTHOR]

This paper reports the results obtained in a Nordic Nuclear Safety Research project during the second intercomparison exercise for the determination of difficult to measure radionuclides in decommissioning waste. Eight laboratories participated by carrying out radiochemical analysis of 3H, 14C, 36Cl, 41Ca, 55Fe and 63Ni in an activated concrete. In addition, gamma emitters, namely 152Eu and 60Co, were analysed. The assigned values were derived from the submitted results according to ISO 13,528 standard and the performance assessments were determined using z scores. The measured results were compared with activation calculation result showing varying degree of comparability. [ABSTRACT FROM AUTHOR]

This paper reports the results obtained during an intercomparison exercise for the determination of difficult to measure radionuclides in activated reactor pressure vessel (RPV) steel samples. In total, eight laboratories participated analysing 14C, 55Fe and 63Ni activity concentrations in RPV steel. In addition, some laboratories also analysed 60Co activity concentrations. Corresponding activity concentrations were also determined using activation calculations. Robust statistical techniques were utilised for the analysis of the results according to ISO 13528 standard. The results showed good agreement for 55Fe and 63Ni results whereas 14C results had significant differences. 60Co results were in quite good agreement. [ABSTRACT FROM AUTHOR]

This work describes the outcomes of the COST Action-TU1301 “NORM4Building” intercomparison on the determination of natural radioactivity in ceramics. Twenty-two laboratories involved in the intercomparison are evaluated for their performance using robust statistics. The reference values of 226 Ra ( 214 Bi and 214 Pb) are determined to be 122 ± 11 Bq kg −1 and 124 ± 14 Bq kg −1 , respectively and in secular equilibrium in the uranium chain while the reference values of 232 Th ( 228 Ac) is determined to be 61 ± 6 Bq kg −1 and that of 40 K was determined to be 955 ± 40 Bq kg −1 . Although the aim of the exercise was to determine the activity concentration of 226 Ra, 232 Th and 40 K and evaluation of the “Activity Concentration Index”, laboratories were asked to report complete characterization of natural radionuclides. The results of this exercise pointed out a good performance among laboratories since the percentage of the acceptable results were above 90% for the radionuclides of interest. Based on these results, considering the systematic rejection of the results reported from a few laboratories we emphasize the need for quality control procedures. [ABSTRACT FROM AUTHOR]

Since 1992, the Spanish and Portuguese-Speaking Working Group of the ISFG (GHEP-ISFG) has been organizing annual Intercomparison Exercises (IEs) coordinated by the Quality Service at the National Institute of Toxicology and Forensic Sciences (INTCF) from Madrid, aiming to provide proficiency tests for forensic DNA laboratories. Each annual exercise comprises a Basic (recently accredited under ISO/IEC 17043: 2010) and an Advanced Level, both including a kinship and a forensic module. Here, we show the results for both autosomal and sex-chromosomal STRs, and for mitochondrial DNA (mtDNA) in two samples included in the forensic modules, namely a mixture 2:1 (v/v) saliva/blood (M4) and a mixture 4:1 (v/v) saliva/semen (M8) out of the five items provided in the 2014 GHEP-ISFG IE. Discrepancies, other than typos or nomenclature errors (over the total allele calls), represented 6.5% (M4) and 4.7% (M8) for autosomal STRs, 15.4% (M4) and 7.8% (M8) for X-STRs, and 1.2% (M4) and 0.0% (M8) for Y-STRs. Drop-out and drop-in alleles were the main cause of errors, with laboratories using different criteria regarding inclusion of minor peaks and stutter bands. Commonly used commercial kits yielded different results for a micro-variant detected at locus D12S391. In addition, the analysis of electropherograms revealed that the proportions of the contributors detected in the mixtures varied among the participants. In regards to mtDNA analysis, besides important discrepancies in reporting heteroplasmies, there was no agreement for the results of sample M4. Thus, while some laboratories documented a single control region haplotype, a few reported unexpected profiles (suggesting contamination problems). For M8, most laboratories detected only the haplotype corresponding to the saliva. Although the GHEP-ISFG has already a large experience in IEs, the present multi-centric study revealed challenges that still exist related to DNA mixtures interpretation. Overall, the results emphasize the need for further research and training actions in order to improve the analysis of mixtures among the forensic practitioners. [ABSTRACT FROM AUTHOR]

Two series of activity standards of 60 Co in cast steel matrix, developed for the calibration of gamma-ray spectrometry systems in the metallurgical sector, were characterised using a European interlaboratory comparison among twelve National Metrology Institutes and one international organisation. The first standard, consisting of 14 disc shaped samples, was cast from steel contaminated during production (“originally”), and the second, consisting of 15 similar discs, from artificially-contaminated (“spiked”) steel. The reference activity concentrations of 60 Co in the cast steel standards were (1.077±0.019) Bq g −1 on 1 January 2013 12h00 UT and (1.483±0.022) Bq g −1 on 1 June 2013 12h00 UT, respectively. [ABSTRACT FROM AUTHOR]

The performance and the uncertainty of receptor models (RMs) were assessed in intercomparison exercises employing real-world and synthetic input datasets. To that end, the results obtained by different practitioners using ten different RMs were compared with a reference. In order to explain the differences in the performances and uncertainties of the different approaches, the apportioned mass, the number of sources, the chemical profiles, the contribution-to-species and the time trends of the sources were all evaluated using the methodology described in Belis et al. (2015). In this study, 87% of the 344 source contribution estimates (SCEs) reported by participants in 47 different source apportionment model results met the 50% standard uncertainty quality objective established for the performance test. In addition, 68% of the SCE uncertainties reported in the results were coherent with the analytical uncertainties in the input data. The most used models, EPA-PMF v.3, PMF2 and EPA-CMB 8.2, presented quite satisfactory performances in the estimation of SCEs while unconstrained models, that do not account for the uncertainty in the input data (e.g. APCS and FA-MLRA), showed below average performance. Sources with well-defined chemical profiles and seasonal time trends, that make appreciable contributions (>10%), were those better quantified by the models while those with contributions to the PM mass close to 1% represented a challenge. The results of the assessment indicate that RMs are capable of estimating the contribution of the major pollution source categories over a given time window with a level of accuracy that is in line with the needs of air quality management. [ABSTRACT FROM AUTHOR]

A new methodology to assess source apportionment model performance in intercomparison exercises, encompassing the preparation of real-world and synthetic datasets and the evaluation of the source apportionment results reported by participants, is described. The evaluation consists of three types of tests: complementary tests, preliminary tests, and performance tests. The complementary tests provide summary information about the source apportionment results as a whole. The preliminary tests check whether source/factors belong to a given source category. Three types of indicators: Pearson correlation (Pearson), standardized identity distance (SID), and weighted difference (WD) are used to test factor/source chemical profiles, while factor/source time series and contribution-to-species values are tested only using the Pearson. The performance tests, based on international standards for proficiency testing, are targeted at evaluating whether the reported biases in the quantification of the factor/source contribution estimates (SCEs) and uncertainties are consistent with previously established quality standards in a fitness-for-purpose approach. Moreover, the consistency of the SCE time series is evaluated using a variant of the RMSE normalised by the reference standard uncertainty. The described methodology facilitates a thorough evaluation of the source apportionment output. The new indicator to compare source or factor profiles presented in this study (SID) is more robust and provides additional information compared to the existing ones. [ABSTRACT FROM AUTHOR]

EURADOS Working Group 6 has organized an intercomparison exercise on the use of the ICRP Reference Computational Phantoms with radiation transport codes. This paper summarizes the results of a specific task from the intercomparison exercise modelling internal radiation sources. The quantities to be calculated were absorbed fractions and specific absorbed fractions for monoenergetic photon and electron sources as well as S-values for two radionuclides in four source organs. Twelve participants from eleven countries participated in this specific task using the Monte Carlo radiation transport codes FLUKA, Geant4, the MCNP code family, PenEasy, TRIPOLI-4 and VMC. Although some participants provided initial solutions in good agreement with the master solution evaluated by the organizers, differences of factors or even orders of magnitude were also found. Following feedback from the organizer, most participants submitted revised solutions that were mostly in better agreement with the master solution, although this was not always the case. Some initial and revised results are discussed in detail in this paper, and the reasons of mistakes are described as far as they were revealed by the participants. A full account of all results is presented in specific annexes as supplemental material. • EURADOS has organized an intercomparison study on the use of the ICRP/ICRU reference computational phantoms. • This article deals with one task involving internal sources. • Some participants provided solutions in agreement with the master solution, but large differences were also found. • Following feedback from the organizer, most participants submitted revised solutions that were mostly in better agreement. • It has been confirmed that intercomparison exercises are valuable for establishing good practice in computational dosimetry. [ABSTRACT FROM AUTHOR]

The improvement of the Monte Carlo (MC) community skills on computational simulations in Medical Physics is crucial to the field of radiotherapy as well as radiology. The Monte Carlo Modelling Expert Group (MCMEG) is an expert network specialized in MC radiation transport modelling and simulation applied to the radiation protection and dosimetry research fields. The MCMEG addressed a multigroup dosimetric intercomparison exercise for modelling and simulating a case of prostate radiation therapy (RT) protocol. This intercomparison was launched in order to obtain the dose distribution in the prostate target volume and in the neighboring organs. Dose assessments were achieved by using TLDs. A protocol using two pair of parallel-opposed fields were planned and performed with Alderson-Rando Pelvic Phantom. The assessed organs at risk were the urinary bladder, rectum and right and left femur heads. The RT simulations were performed using the MCNPx, MCNP6 and egs++ and BEAMnrc/DOSXYZnrc modules of EGSnrc Monte Carlo codes. The dose to the target volume, mean doses and standard deviation in the organs at risk, and dose volume data were computed. A comparison between the simulated results and the experimental values obtained from TLD measurements was made. In some cases the results obtained using MC simulations showed large deviations in comparison to the results obtained from the TLD measurements and these variations can be explained by the difficulties in the modelling of the geometry, selection of MC parameters required for the simulations and the statistical errors and inaccuracies in experimental measurements. Even though, the exercise has been a great opportunity for the MC groups to learn and share the main difficulties found during the modelling and the analysis of the results. Concerned to the obtained variations, the MCMEG team consider that this was expected for the level of complexity of the exercise and must be studied by the MC groups. • The Monte Carlo Modelling Expert Group (MCMEG). • Intercomparison exercise of dose assessments achieved with TLDs. • Simulations using the MCNPx, MCNP6 and EGSnrc and BEAMnrc/DOSXYZnrc MC codes. • MCMEG team consider that this was expected for the level of complexity of the exercise and must be studied by the MC groups. [ABSTRACT FROM AUTHOR]