B. Merk

发表

Simulation of thermal fluid dynamics in parabolic trough receiver tubes with direct steam generation using the computer code ATHLET

R. Pitz-Paal, T. Hirsch, A. Hoffmann, 2014 .

Multiple Timescale Expansions for Neutron Kinetics—I: Illustrative Application to the Point-Kinetics Model

D. Cacuci, B. Merk, 2005 .

Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR

E. Fridman, U. Rohde, B. Merk, 2011 .

On the numerical modelling of frozen walls in a molten salt fast reactor

D. Emerson, A. Skillen, C. Moulinec, 2019, Nuclear Engineering and Design.

Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

J. Kloosterman, D. Lathouwers, D. Heuer, 2019, EPJ Nuclear Sciences & Technologies.

Part 3: Evaluating a small modular high temperature reactor design during control rod withdrawal and a depressurised loss of coolant accidents

B. Merk, T. Aoki, D. Litskevich, 2021 .

The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor

B. Merk, D. Litskevich, Gregory Cartland-Glover, 2020, Energies.

The Role of Nuclear Power in Meeting Current and Future Industrial Process Heat Demands

A. Peakman, B. Merk, 2019, Energies.

Small modular high temperature reactor optimisation – Part 1: A comparison between beryllium oxide and nuclear graphite in a small scale high temperature reactor

B. Merk, T. Abram, D. Litskevich, 2019, Progress in Nuclear Energy.

Evaluation of BWR Burnup Calculations Using Deterministic Lattice Codes SCALE-6.2, WIMS-10A and CASMO5

A. Peakman, J. Liang, B. Merk, 2020, Energies.

Solutions without Space-Time Separation for ADS Experiments: Overview on Developments and Applications

B. Merk, V. Glivici-Cotruţă, 2012 .

AN ANALYTICAL SOLUTION FOR AN EXTERNAL SOURCE PROBLEM WITH DELAYED NEUTRONS USING THE TELEGRAPHERS EQUATION

F. Weiss, B. Merk, Forschungszentrum Dresden-Rossendorf, 2009 .

Burnup Credit Evaluation for BWR Spent Fuel from Full Core Calculations

A. Peakman, B. Merk, Anna Detkina, 2020, Applied Sciences.

An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies

U. Rohde, B. Merk, 2012 .

AN ANALYTICAL SOLUTION FOR THE CONSIDERATION OF THE EFFECT OF ADJACENT FUEL ELEMENTS

U. Rohde, B. Merk, 2011 .

SP3 Solution versus Diffusion Solution in Pin-by-Pin Calculations and Conclusions Concerning Advanced Methods

B. Merk, D. Litskevich, 2014 .

Fine Distributed Moderating Material with Improved Thermal Stability Applied to Enhance the Feedback Effects in SFR Cores

B. Merk, 2013 .

An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production

B. Merk, 2009 .

Optimization of the pre-conceptual design of the MSFR

O. Geoffroy, J. L. Kloosterman, Danny Lathouwers, 2013 .

Criticality Analysis for BWR Spent Fuel Based on the Burnup Credit Evaluation from Full Core Simulations

A. Peakman, B. Merk, Anna Detkina, 2021, Applied Sciences.

On the Employment of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 1: Thermophysical Properties and Core Criticality

B. Merk, D. Litskevich, Gregory Cartland-Glover, 2022, Energies.

On the Use of a Molten Salt Fast Reactor to Apply an Idealized Transmutation Scenario for the Nuclear Phase Out

U. Rohde, B. Merk, D. Litskevich, 2014, PLoS ONE.

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

B. Merk, 2013 .

A HELIOS-Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium-Based Initial Core for iMAGINE

B. Merk, D. Litskevich, Anna Detkina, 2022, Energies.

A First Step towards Zero Nuclear Waste—Advanced Strategic Thinking in Light of iMAGINE

C. Degueldre, B. Merk, D. Litskevich, 2022, Energies.

A HELIOS-Based Dynamic Salt Clean-Up Study for iMAGINE

B. Merk, D. Litskevich, Anna Detkina, 2022, Applied Sciences.

On the Dimensions Required for a Molten Salt Zero Power Reactor Operating on Chloride Salts

B. Merk, D. Litskevich, S. Atkinson, 2021, Applied Sciences.

A disruptive approach to eliminating weapon-grade plutonium – Pu burning in a molten salt fast reactor

B. Merk, D. Litskevich, 2018, PloS one.

Demand driven salt clean-up in a molten salt fast reactor – Defining a priority list

A. Mount, R. Gregg, B. Merk, 2018, PloS one.

An innovative way of thinking nuclear waste management – Neutron physics of a reactor directly operating on SNF

Bruno Merk, Mark Bankhead, Dzianis Litskevich, 2017, PloS one.

On a long term strategy for the success of nuclear power

Bruno Merk, Dzianis Litskevich, Richard J. K. Taylor, 2017 .

Transmutation of All German Transuranium under Nuclear Phase Out Conditions – Is This Feasible from Neutronic Point of View?

B. Merk, D. Litskevich, 2015, PloS one.

On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study

B. Merk, D. Litskevich, 2015 .

Progress in reliability of fast reactor operation and new trends to increased inherent safety

Robert Hill, P. Chellapandi, Bruno Merk, 2015 .

Neutron shielding studies on an advanced molten salt fast reactor design

B. Merk, J. Konheiser, 2014 .

On the use of moderating material to enhance the feedback coefficients in SFR cores with high minor actinide content

F. Weiss, B. Merk, 2012 .

Use of Zirconium-Based Moderators to Enhance Feedback Coefficients in a MOX-Fueled Sodium-Cooled Fast Reactor

E. Fridman, F. Weiss, B. Merk, 2012 .

Analysis of the influence of different arrangements for ZrH moderator material on the performance of a SFR core

F. Weiss, B. Merk, 2011 .

On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors

E. Fridman, F. Weiss, B. Merk, 2011 .

IMAGINE - A Disruptive Change to Nuclear or How Can We Make More Out of the Existing Spent Nuclear Fuel and What Has to be Done to Make it Possible in the UK?

A. Peakman, B. Merk, D. Litskevich, 2019 .

Advanced micro-reactor concepts

A. Peakman, B. Merk, Z. Hodgson, 2018, Progress in Nuclear Energy.

A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution

Bruno Merk, Dzianis Litskevich, Anna Detkina, 2021, Energies.

Verification of the current coupling collision probability method with orthogonal flux expansion for the case of single cell

B. Merk, D. Litskevich, S. Atkinson, 2020 .

Assessment of High-Electrification UK Scenarios with Varying Levels of Nuclear Power and Associated Post-Fault Behaviour

Vincenzo Trovato, Bruno Merk, Aiden Peakman, 2021, Energies.

A Three-Scale Expansion Solution for a Time-Dependent P1 Neutron Transport Problem with External Source

F. Weiss, B. Merk, 2009 .

Multiple Timescale Expansions for Neutron Kinetics—II: Illustrative Application to P1 and P3 Equations

D. Cacuci, B. Merk, 2005 .

Multi scale approximation of the time-dependent boltzmann equation

D. Cacuci, B. Merk, 2005 .

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)

Ulrich Rohde, Bruno Merk, Dzianis Litskevich, 2021, Energies.

On a Roadmap for Future Industrial Nuclear Reactor Core Simulation in the U.K. to Support the Nuclear Renaissance

Bruno Merk, Mark Bankhead, Dzianis Litskevich, 2018, Energies.

Development and verification of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR

Soeren Kliem, Ulrich Rohde, Silvio Baier, 2012 .

iMAGINE—Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century

B. Merk, D. Litskevich, Anna Detkina, 2023, Energies.

Overview of major HZDR developments for fast reactor analysis

Soeren Kliem, Ulrich Rohde, S. Duerigen, 2013 .

A MODERATION LAYER TO IMPROVE THE SAFETY BEHAVIOR OF SODIUM COOLED FAST REACTORS

F. Weiss, B. Merk, Forschungszentrum Dresden-Rossendorf, 2011 .