Adamsson, C., and H. Anglart. “A Sensitivity Study of Lagrangian Models for Application to Annular Two-Phase Flows.” In Nuclear Energy for New Europe 2007. Portoroz, 2007.

Adamsson, C., and J. M. Le Corre. “Transient Dryout Prediction Using a Computationally Efficient Method for Sub-Channel Film-Flow Analysis.” Nuclear Engineering and Design. Accessed November 1, 2014. doi:10.1016/j.nucengdes.2014.09.012.

Adamsson, Carl. Dryout and Power Distribution Effects in Boiling Water Reactors. Stockholm: Skolan för teknikvetenskap, Kungliga Tekniska högskolan, 2009. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-11343.

———. Measurements of Film Flow Rate in Heated Tubes with Various Axial Power Distributions. Stockholm: Fysik, 2006. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-3881.

Adamsson, Carl, and Henryk Anglart. “A Reinterpretation of Measurements in Developing Annular Two-Phase Flow.” Nuclear Engineering and Design 241, no. 11 (November 2011): 4562–67. doi:10.1016/j.nucengdes.2011.01.002.

———. “An Investigation of Cross-Section Geometry Effects on the Deposition Rate in Annular Two-Phase Flows with a Lagrangian Model.” In The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), 2007.

———. “Dryout Predictions in BWR Fuel Assemblies with Spacers.” In Proceedings of the Sixth International Conference on Nuclear Thermal-Hydraulics, Operation and Safety, 2004. http://kth.diva-portal.org/smash/record.jsf?pid=diva2:495230.

———. “Experimental Investigation of the Liquid Film for Annular Flow in a Tube with Various Axial Power Distributions.” In The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11). Avignon, France, 2005.

———. “Film Flow Measurements for High-Pressure Diabatic Annular Flow in Tubes with Various Axial Power Distributions.” Nuclear Engineering and Design 236, no. 23 (December 2006): 2485–93. http://www.sciencedirect.com/science/article/B6V4D-4JT9CTJ-1/2/9a142dd7df707167ea43ef3051c1cb24.

———. “Influence of Axial Power Distribution on Dryout: Film-Flow Models and Experiments.” Nuclear Engineering and Design 240, no. 6 (June 2010): 1495–1505. doi:10.1016/j.nucengdes.2010.02.013.

———. “Lagrangian Modeling of Dispersion and Deposition of Drops in Annular Flow.” KTH, Stockholm, Sweden, 2006.

———. “Measurements of the Liquid Film Flow Rate in High Pressure Annular Flow with Various Axial Power Distributions,” 2005. http://kth.diva-portal.org/smash/record.jsf?pid=diva2:325305.

Adamsson, Carl, Henryk Anglart, Magnus Nordsveen, and Norbert Hoyer. “The MONA Subchannel Analysis Code – Part B: Validation And Verification.” In The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), 2003.

Adamsson, Carl, and Jean-Marie Le Corre. “MEFISTO - A Mechanistic Tool for the Prediction of Critical Power in BWR Fuel Assemblies.” In Proceedings of the 16th International Conference on Nuclear Engineering (ICONE 16). Orlando, Florida, USA, 2008.

———. “Modeling and Validation of a Mechanistic Tool (MEFISTO) for the Prediction of Critical Power in BWR Fuel Assemblies.” Nuclear Engineering and Design 241, no. 8 (August 2011): 2843–58. doi:16/j.nucengdes.2011.01.033.

———. “On a Best-Estimate Approach to the Calculation of Dryout Probability during BWR Transients.” In Proceedings the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), 2011.

———. “Validation of Film Flow Analysis Code MEFISTO with NUPEC/BFBT Critical Power Measurements.” In The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 2009.

———. “VIPRE-W / MEFISTO-T – A Mechanistic Tool for Transient Prediction of Dryout in BWR Fuel.” In Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), 2011.

Adamsson, Carl, Davide Papini, Omar Zerkak, and Horst-Michael Prasser. “Simulation of Complex Transient Flow Patterns in the ESBWR Passive Containment Cooling System.” In Proceedings of the 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9). Kaohsiung, Taiwan, 2012.

———. “Simulation of International Standard Problem ISP-42, Phase B, Using In-House Coupled Code GOTHIC-TRACE.” In Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-15. Pisa, Italy, 2013.

———. “Simulation of International Standard Problem ISP-42, Phases A and B with the TRACE Code.” In Proceedings of the 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9). Kaohsiung, Taiwan, 2012.

Bergmann, U., C. Adamsson, and G. Norbäck. “Advanced Dryout Correlation and CPR Methodology for Westinghouse SVEA-96 Optima3 Fuel.” In American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV, 1:209–25, 2009. http://www.scopus.com/inward/record.url?eid=2-s2.0-74549133041&partnerID=40&md5=8c64b1301846abc426df6789b6ed9ec7.

Brynjell-Rahkola, Karolina, Jean-Marie Le Corre, and Carl Adamsson. “Validation of VIPRE-W Sub-Channel Void Predictions Using NUPEC/BFBT Measurements.” In Proceedings of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 2009.

Caraghiaur, Diana, Carl Adamsson, and Henryk Anglart. “A Model for Inertial Drop Deposition Suitable to Predict Obstacle Effect.” Nuclear Engineering and Design 260 (July 2013): 121–33. doi:10.1016/j.nucengdes.2013.03.010.

———. “Deposition of Inertial Drops in Eulerian Formulation.” In Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-15. Pisa, Italy, 2013.

Caraghiaur, Diana, Carl Adamsson, and Heryk Anglart. “Verification of the Applicability of Random Walk Models to Calculate Drop Deposition in Nuclear Fuel Assemblies.” In The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13). Kanazawa City, Ishikawa Prefecture, Japan, 2009.

Helmersson, Sture, Majed Mahdi, Gunilla Norb, Dmitry Paramonov, Rolf Eklund, and Carl Adamsson. Method and apparatus of estimating dryout properties in a nuclear light ... 7760842, issued July 20, 2010. http://www.google.se/patents?hl=sv&lr=&vid=USPAT7760842&id=ij3SAAAAEBAJ&oi=fnd&dq=%22carl+adamsson%22&printsec=abstract.

Holmkvist, Carolin. Kvantifiering av osäkerheter i lyftkraftsmodellen, 2014. http://www.diva-portal.org/smash/record.jsf?dswid=5557&pid=diva2%3A774190&c=1&searchType=SIMPLE&language=en&query=carolin+holmkvist&af=%5B%5D&aq=%5B%5B%5D%5D&aq2=%5B%5B%5D%5D&aqe=%5B%5D&noOfRows=50&sortOrder=author_sort_asc&onlyFullText=false&sf=all&jfwid=5557.

Krejci, Marko, Carl Adamsson, and Henryk Anglart. “Development of a Model for Prediction of Annular Flow and Dryout in BWR Fuel Assemblies with Spacers.” In Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11). Avignon, France, 2005.

Le Corre, J.M., I. Trisic, D. Palko, C. Adamsson, and H. Anglart. “Transient Responses and Analyses of Three Thermal-Hydraulic Models to Typical BWR Accident Scenarios.” In Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15. Pisa, Italy, 2013.

Le Corre, Jean-Marie, and C. Adamsson. “Validation of a Mechanistic Tool for the Prediction of Critical Power in BWR Fuel Assemblies.” In The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), Seoul, Korea, October 5-9, 2008, 2008.

Le Corre, Jean-Marie, and Carl Adamsson. “Development of a New Mechanistic Tool for the Prediction of the Liquid Film Dryout during a Transient.” In The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 2009.

Le Corre, Jean-Marie, Carl Adamsson, and Pablo Alvarez. “Transient Void, Pressure Drop and Critical Power BFBT Benchmark Analysis and Results with VIPRE-W/MEFISTO-T.” In Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), 2011.

Leng, Jinzhen. An Investigation of Transient Application of CHF Correlations. Trita-FYS, 0280-316X ; 2008:4. Stockholm: Fysik, Kungliga Tekniska högskolan, 2008.

Norbäck, Gunilla, and Carl Adamsson. Methods and Devices Relating to a Nuclear Light Water Reactor of the Boiling ... Accessed December 30, 2010. http://www.google.se/patents?hl=sv&lr=&vid=USPATAPP12244812&id=ZCfJAAAAEBAJ&oi=fnd&dq=%22carl+adamsson%22&printsec=abstract.

Nordström, Jan, Karl Forsberg, Carl Adamsson, and Peter Eliasson. “Finite Volume Methods, Unstructured Meshes and Strict Stability for Hyperbolic Problems.” Applied Numerical Mathematics 45, no. 4 (June 2003): 453–73. doi:10.1016/S0168-9274(02)00239-8.

Nordsveen, M., N. Hoyer, H. Anglart, and C. Adamsson. “The MONA Subchannel Analysis Code  –  Part  A: Model  Description.” In The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), 2003.

Papini, Davide, Carl Adamsson, Michele Andreani, and Horst-Michael Prasser. “Assessment of GOTHIC and TRACE Codes against Selected PANDA Experiments on a Passive Containment Condenser.” Nuclear Engineering and Design 278 (October 15, 2014): 542–57. doi:10.1016/j.nucengdes.2014.08.007.

———. “Simulation of International Standard Problem ISP-42, Phase B Using the Containment Code GOTHIC.” In Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-15. Pisa, Italy, 2013.

———. “Study of Condensation Heat Transfer in Passive Safety Systems Using GOTHIC and TRACE Codes.” In Proceedings of the 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), 2012.

Paramonov, D., and C. Adamsson. “Advanced Dryout Correlation for BWR Fuel.” In 18th International Conference on Nuclear Engineering, Proceedings, ICONE-18, 777–83, 2010.

Secondi, F., C. Adamsson, and J.-M. Le Corre. “An Assessment of Entrainment Correlations for Dryout Prediction in BWR Fuel Bundles.” In 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), Kanazawa, Japan, 2009.