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Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system

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• Nuclear Engineering and Design 241(2011)9, 3777-3786
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Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR

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Super-homogenisation factors in pinwise calculations by the reactor dynamics code DYN3D

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• Annals of Nuclear Energy 38(2011), 2111-2119

On the use of the Serpent Monte Carlo code for few-group cross section generation

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Development of Multi-Physics Code Systems based on the Reactor Dynamics Code DYN3D

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• Contribution to proceedings
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Use of the local Pu-239 concentration as an indicator of burnup spectral history in DYN3D

Bilodid, I.; Mittag, S.

• Annals of Nuclear Energy 37(2010), 1208-1213
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ATWS analysis for PWR using the coupled code system DYN3D/ATHLET

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• Annals of Nuclear Energy 36(2009), 1230-1234
  DOI: 10.1016/j.anucene.2009.04.001⁽¹⁰⁶⁾
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Simulation von ATWS-Transienten in Druckwasserreaktoren

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• Contribution to proceedings
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• Invited lecture (Conferences)
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Dynamics of Molten Salt Reactors

Krepel, J.; Grundmann, U.; Rohde, U.; Weiss, F.-P.

• Nuclear Technology 164(2008), 34-44

Development and verification of a nodal approach for solving the multigroup SP3 equations

Beckert, C.; Grundmann, U.

• Annals of Nuclear Energy 35(2008)1, 75-86

DYN3D - Advanced Reactor Simulations in 3D

Rohde, U.; Grundmann, U.; Kliem, S.

• Nuclear Energy Review 2(2007), 28-30
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Multigroup Diffusion and SP3 Solutions for a PWR MOX/UO2 Benchmark with the Code DYN3D

Beckert, C.; Grundmann, U.; Mittag, S.

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• Lecture (Conference)
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DYN3D-MSR spatial dynamics code for Molten Salt Reactors

Krepel, J.; Rohde, U.; Grundmann, U.; Weiß, F.-P.

• Annals of Nuclear Energy 34(2007), 449-462

Calculation of the VVER-1000 Coolant Transient Benchmark using the Coupled Code Systems DYN3D/RELAP5 and DYN3D/ATHLET

Kozmenkov, Y.; Kliem, S.; Grundmann, U.; Rohde, U.; Weiss, F.-P.

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Analyses of the V1000CT-1 benchmark with the DYN3D/ATHLET and DYN3D/RELAP coupled code systems including a coolant mixing model validated against CFD calculations

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  DOI: 10.1016/j.pnucene.2006.06.008⁽¹⁰⁸⁾
  Cited 26 times in Scopus

DYN1D-MSR dynamics code for molten salt reactors

Krepel, J.; Rohde, U.; Grundmann, U.; Weiss, F.-P.

• Annals of Nuclear Energy 32(2005)17, 1799-1824
  DOI: 10.1016/j.anucene.2005.07.007⁽¹⁰⁹⁾
  Cited 56 times in Scopus

Validation of coupled codes using VVER plant measurements

Vanttola, T.; Hämäläinen, A.; Kliem, S.; Kozmenkov, Y.; Weiß, F.-P.; Kereszturi, A.; Hadek, J.; Strmensky, C.; Stefanova, S.; Kuchin, A.

• Nuclear Engineering and Design 235(2005), 507-519 (2005)

Core response of a PWR to a slug of under-borated water

Kliem, S.; Rohde, U.; Weiß, F.-P.

• Nuclear Engineering and Design 230(2004), 121-132
  DOI: 10.1016/j.nucengdes.2003.11.021⁽¹¹⁰⁾
  Cited 30 times in Scopus

Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D

Grundmann, U.; Kliem, S.⁽¹¹¹⁾; Rohde, U.

• Nuclear Science and Engineering 148(2004), 226-234

Discontinuity factors for non-multiplying material in two-dimensional hexagonal reactor geometry

Mittag, S.; Petkov, P.; Grundmann, U.

• Annals of Nuclear Energy 30/13 (2003) pp. 1347-1364

Analyses of the OECD Main Steam Line Break Benchmark with the Codes DYN3D and ATHLET

Grundmann, U.; Kliem, S.

• Nuclear Technology 142(2003) 146-153

The Modeling of Fuel Rod Behaviour under RIA Conditions in the Code DYN3D

Rohde, U.

• Annals of Nuclear Energy 28 (2001), Vol. 13, pp. 1343-1363

Experimental Investigations on the Four-Loop Test Facility ROCOM

Höhne, T.; Grunwald, G.; Prasser, H.-M.

• Kerntechnik 65/5-6, S. 212-215

Comparative Study of a Boron Dilution Scenario in VVER Reactors

Ivanov, K. N.; Grundmann, U.; Mittag, S.; Rohde, U.

• Annals of Nuclear Energy 26 (1999) 1331-1339

A Two-Dimensional Intranodal Flux Expansion Method for Hexagonal Geometry

Grundmann, U.; Hollstein, F.

• Nuclear Science and Engineering 133 (1999) 201-212

Analysis of a boron dilution accident for WWER-440 combining the use of the codes DYN3D and SiTAP

Rohde, U.; Elkin, I.; Kalinenko, V.

• Nuclear Engineering and Design 170 (1997), pp. 95 - 99

Neutron Flux Reconstruction ina Hexagonal Cassete - Theory and Implementation into the Code DYN3D/H1.1

Hadek, J.; Grundmann, U.

• Nucleon No. 3, (1997), pp. 8 - 14