Staffan Qvist
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Currently working on:
* Code development for optimized fast reactor design
* Reactivity feedbacks analysis and methods for breed-and-burn / traveling wave reactors
* Designing and building experiments for steel corrosion science in high temperature oxygen controlled liquid lead-bismuth-eutectic under irradiation
* Neutronic burnup effects in metallic nuclear fuel (U-Zr/U-Pu-Zr)
* Inherent reactivity feedback safety and thermostating load-following control systems for low leakage fast reactors
Tools
The ADOPT code, a complete fast reactor design and analysis tool. Email staffan@berkeley.edu to obtain a license agreement - code and manual is then distributed by email.
Matlab script for calculating the density of metallic (U-Zr) fuel at temperatures between 50-900 deg.C for any Zr-fraction. Download. (Based on a new correlation developed for the ADOPT code)
Proceedings from the "SERPENT monte-carlo code workshop"
hosted at UC Berkeley on the 1st and 2nd of May 2012:
1. The UCB Nuc. Eng. Dept. computational capabilities - Ryan Bergmann, UCB
2. The SERPENT code - Jaakko Leppänen, VTT
3. The ADOPT code for optimized fast reactor core design - Staffan Qvist, UCB
4. The BEAU methodology for equilibrium composition search - Tommy Cisneros, UCB
5. SERPENT depletion methods - Jaakko Leppänen, VTT
6. Use of GPUs for monte-carlo calculations - Ryan Bergmann, UCB
7. 3D visualization & modeling for monte-carlo - Noah Fischer, UCB
8. Sensitivity, Uncertainty and Representivity Analysis - Jeff Seifried, UCB/LLNL
9. Hybrid MC-MOC, Common Ray Tracing Algorithms - Jasmina Vujic, UCB
10. Group constant generation capabilites in SERPENT - Jaakko Leppänen, VTT
11. Use of SERPENT for generating XSs for PARCS - Andrew Hall, U Michigan
12. SERPENT version 2 and future plans - Jaakko Leppänen, VTT
Proceedings from the "Seminar on lead-cooled nuclear technology"
hosted at UC Berkeley on the 4th of November 2011:
1. Introduction and welcome - Staffan Qvist, UC Berkeley, US
2. Swedish LFR research - Jan Wallenius, KTH, Sweden
3. US LFR research - Craig Smith, NPS, US
4. Japanese LFR research - Hiroshi Sekimoto, TiTECH, Japan / UC Berkeley, US
5. Korean LFR research - Yonghee Kim, KAIST, South Korea
6. The ENHS reactor - Ehud Greenspan, UC Berkeley, US
7. Nuclear fuel for lead cooled reactors - Erdenechimeg Suvdantsetseg, KTH, Sweden
8. Material issues and solutions for HLM technology - Peter Hosemann, UC Berkeley, US
9. The ICE2 HLM experiment station - Staffan Qvist, UC Berkeley, US
10. The LANL delta-loop - Keith Woloshun, LANL, US
11. CFD for HLM reactors - Roman Thiele, KTH, Sweden
