Home / Publications / Journals / Nuclear Technology / Volume 210 / Number 9
An Assessment of Deep Borehole Disposal Post-Closure Safety
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1511-1534
Research Article / dx.doi.org/10.1080/00295450.2023.2266609
Natural Analogue Studies in Support of Post-Closure Safety Assessment of Deep Geological Disposal
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1535-1548
Research Article / dx.doi.org/10.1080/00295450.2023.2240160
Assessing the Consequences of Postclosure Criticality in Spent Nuclear Fuel
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1549-1566
Research Article / dx.doi.org/10.1080/00295450.2023.2277028
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1567-1577
Research Article / dx.doi.org/10.1080/00295450.2024.2304910
Modeling Geologic Waste Repository Systems Below Residual Saturation
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1578-1592
Research Article / dx.doi.org/10.1080/00295450.2023.2262294
Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1593-1601
Research Article / dx.doi.org/10.1080/00295450.2024.2329834
A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1602-1622
Research Article / dx.doi.org/10.1080/00295450.2023.2287307
Roadmap of Graphite Moderator and Graphite-Matrix TRISO Fuel Management Options
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1623-1638
Research Article / dx.doi.org/10.1080/00295450.2024.2337311
Drying of Spent Nuclear Fuel: Considerations and Examples
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1639-1647
Research Article / dx.doi.org/10.1080/00295450.2023.2226519
Computation of Particulate Deposition on Dry Storage Canisters
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1648-1657
Research Article / dx.doi.org/10.1080/00295450.2023.2299892
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1658-1671
Research Article / dx.doi.org/10.1080/00295450.2023.2291605
Measurement of Aerosol Transmission Through a Stress Corrosion Crack–Like Geometry
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1672-1684
Research Article / dx.doi.org/10.1080/00295450.2024.2302727
Package Performance Study: A Historical Perspective and Planning for a Path Forward
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1685-1693
Research Article / dx.doi.org/10.1080/00295450.2023.2232988
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1694-1705
Research Article / dx.doi.org/10.1080/00295450.2023.2240185
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1706-1721
Research Article / dx.doi.org/10.1080/00295450.2023.2229566
A Sociotechnical Readiness Level Framework for the Development of Advanced Nuclear Technologies
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1722-1739
Research Article / dx.doi.org/10.1080/00295450.2024.2336355
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1740-1747
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1748-1753
Consent-Based Siting of Spent Fuel Facilities: Evidence from Nationwide U.S. Surveys
Nuclear Technology / Volume 210 / Number 9 / September 2024 / Pages 1754-1766