Studsvik (Sweden)

Recent papers from Studsvik (Sweden)

1. Benchmarking of the CMS5 Code System for the NEA/OECD Watts Bar Unit 1 Multi-Cycle Depletion ProblemNuclear Science and Engineering · 2026
2. The Even Moment Method for Solving the P N Form of the Neutron Transport Equation and Challenges in Computing Multi-Group Transport Cross Sections with Anisotropic ScatteringNuclear Science and Engineering · 2026
3. Studsvik’s Core Management System 5: Overview and Recent DevelopmentsNuclear Technology · 2026
4. Reverse transcriptase mediated signal amplification in ligand binding assays.2026
5. Oxidation-Driven Lithium Uptake in Nickel-Base Alloys – Smoking-Gun Evidence for an Inner Cathode under LWR ConditionsJournal of Nuclear Materials · 2026
6. Comparison of Direct Arylation and Zinc-Mediated Polymerizations for Naphthalenediimide–Bithiazole Polymers with Focus on Efficiency, Structure and Green MetricsChemistry of Materials · 2026
7. The 0E2 benchmarks for PWR UO 2 decay heat: an analysis from the NEA WPNCSEPJ Nuclear Sciences & Technologies · 2026
8. Raman spectroscopy study of the influence of additives (Cr-, Cr/Al-, and Gd) on UO2 dissolution behaviorMRS Advances · 2025
9. New synthetic pathway towards BTrzPhen-tetraol: a hydrophilic 2,9-bis-triazolyl-1,10-phenanthroline ligand for selective americium strippingDalton Transactions · 2025
10. Uranium Body Clearance Kinetics—A Long-term Follow-up Study of Retired Nuclear Fuel WorkersHealth Physics · 2024
11. Stress-corrosion cracking sensitization by hydrogen upon oxidation of nickel-base alloys by water – An experiment-guided first-principles studyJournal of Nuclear Materials · 2024
12. How irradiation promotes intergranular stress corrosion crack initiationProgress in Materials Science · 2024
13. Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONENuclear Technology · 2023
14. Crystallographic characterization of U2CrN3: A neutron diffraction and transmission electron microscopy approachNuclear Materials and Energy · 2023
15. Assessment of flow-assisted corrosion rate of copper alloy cooling tube for application in fusion reactorsNuclear Materials and Energy · 2023
16. Performance evaluation of a novel gamma transmission micro-densitometer for PIE of nuclear fuelAnnals of Nuclear Energy · 2023
17. Outward FDI: Determinants and Flows in Emerging Economies: Evidence from ChinaChina and WTO Review · 2022
18. Nanoscale chemistry of Zircaloy-2 exposed to three and nine annual cycles of boiling water reactor operation — an atom probe tomography studyJournal of Nuclear Materials · 2022
19. An Exploratory In Vitro Study of the Effect on Pharyngograms of Acoustic Leaks Through the Velopharyngeal PortJournal of Dental Sleep Medicine · 2021
20. Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grainsJournal of Nuclear Materials · 2021