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Journal Articles

The Application of radiochronometry during the 4th collaborative materials exercise of the nuclear forensics international technical working group (ITWG)

Kristo, M. J.*; Williams, R.*; Gaffney, A. M.*; Kayzar-Boggs, T. M.*; Schorzman, K. C.*; Lagerkvist, P.*; Vesterlund, A.*; Rameb$"a$ck, H.*; Nelwamondo, A. N.*; Kotze, D.*; et al.

Journal of Radioanalytical and Nuclear Chemistry, 315(2), p.425 - 434, 2018/02

 Times Cited Count:14 Percentile:81.7(Chemistry, Analytical)

In a recent international exercise, 10 international nuclear forensics laboratories successfully performed radiochronometry on three low enriched uranium oxide samples, providing 12 analytical results using three different parent-daughter pairs serving as independent chronometers. The vast majority of the results were consistent with one another and consistent with the known processing history of the materials. In general, for these particular samples, mass spectrometry gave more accurate and more precise analytical results than decay counting measurements. In addition, the concordance of the $$^{235}$$U-$$^{231}$$Pa and $$^{234}$$U-$$^{230}$$Th chronometers confirmed the validity of the age dating assumptions, increasing confidence in the resulting conclusions.

Journal Articles

Achievements on oxide and nitride ADS fuels within the European project; EUROTRANS

Delage, F.*; Arai, Yasuo; Belin, R.*; Chen, X.*; D'Agata, E.*; Hania, R.*; Klaassen, F.*; Maschek, W.*; Oigawa, Hiroyuki; Ottaviani, J. P.*; et al.

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 8 Pages, 2011/12

The European FP-6 integrated project EUROTRANS was devoted to management of high-level wastes from nuclear power plants, focusing on MA transmutation in ADS. The object of the project was the assessment of the design and feasibility of an industrial ADS prototype dedicated to MA transmutation. JAEA joined in the project as one of partners. This paper summarizes the ADS fuel development carried out in this project. As for the oxide fuel, a primary candidate, the results of design study, performance in normal operation, safety analysis, irradiation tests and out-of-pile property measurements are described. As for the nitride fuel, an alternative of oxide fuel, the results of irradiation tests and out-of-pile property measurements, and the progress of pyrochemical process for spent fuel treatment are described.

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