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Sökning efter: Sophie Grape 31 träffar

Titel Författare År Språk
21 Spent fuel characterization research at Uppsala University - Presented at kick-off meeting for IAEA CRP on spent fuel characterisation, 2021-02-16 Peter Jansson 2021 Engelska
22 Evaluating Peak Area Uncertainties in Connection to Passive Gamma Measurements of Spent Nuclear Fuel 2021 24-28 October Spain Santander TopFuel 2021 Virginie Solans 2021 Engelska
23 Nuclear Safeguards Assessments For Verification Of Regular And Non-Regular Light Water Reactor Fuel Vaibhav Mishra 2021 Engelska
24 Coincidence spectroscopy for increased sensitivity in radionuclide monitoring Uppsala & Online 19-22 October 2022 The first annual conference of the Alva Myrdal Centre for Nuclear Disarmament Peter Andersson 2022 Engelska
25 State-of-the-Art Report - Prepared by Working Group 4: Technical nuclear non-proliferation and safeguards under the Alva Myrdal Centre for nuclear disarmament Sophie Grape 2022 Engelska
26 Development of a PhD course in verification of nuclear test explosions under AMC Uppsala & Online 19-22 October 2022 The first annual conference of the Alva Myrdal Centre for Nuclear Disarmament Sophie Grape 2022 Engelska
27 Prediction of fuel salt composition using fuel data libraries developed for the Molten Salt Demonstration Reactor 31 October–4 November 2022 Austria Vienna Symposium on International Safeguards: Reflecting on the Past and Anticipating the Future Vaibhav Mishra 2022 Engelska
28 Research on safeguarding molten salt reactor systems at Uppsala University 25-26 August 2022 Stockholm SAINT Workshop Vaibhav Mishra 2022 Engelska
29 Serpent modelling of pressurized heavy water CANDU reactors Cecilia Gustavsson 2023 Engelska
30 Applied nuclear physics in the Alva Myrdal Centre for nuclear disarmament - Non-proliferation and safeguards activities 20-24 March 2023. Germany Dresden 86th Annual Conference of the DPG and DPG Spring Meeting : Section: Matter and Cosmos (SMuK23) Sophie Grape 2023 Engelska
31 Nuclear safeguards directed to the application of multivariate analysis techniques to existing and future nuclear fuel cycles Vaibhav Mishra 2023 Engelska

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