Publications
2024
On the Use of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 3; Radiation Damage
Noori-kalkhoran, O., Jain, L., & Merk, B. (n.d.). On the Use of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 3; Radiation Damage. Energies, 17(19), 4772. doi:10.3390/en17194772
The Need of Chloride-37 Enrichment for Molten Salt Fast Reactors
A Draft Design of a Zero-Power Experiment for Molten Salt Fast Reactor Studies
Merk, B., Noori-kalkhoran, O., Jain, L., Aflyatunova, D., Jones, A., Powell, L., . . . Lange, C. (n.d.). A Draft Design of a Zero-Power Experiment for Molten Salt Fast Reactor Studies. Energies, 17(11), 2678. doi:10.3390/en17112678
On the Employment of a Chloride or Floride Salt Fuel System in Advanced Molten Salt Reactors, Part 2; Core Inventory, Fuel Burnup, and Salt Clean-Up System
Noori-kalkhoran, O., Jain, L., Powell, L., Jones, A., Aflyatunova, D., & Merk, B. (2024). On the Employment of a Chloride or Floride Salt Fuel System in Advanced Molten Salt Reactors, Part 2; Core Inventory, Fuel Burnup, and Salt Clean-Up System. Energies, 17(6), 1475. doi:10.3390/en17061475
A Draft Design of a Zero Power Experiment for Molten Salt Fast Reactor Studies
From Fishing Village to Atomic Town and present: A grounded theory study
NAUTILUS: A Project for the Development of Experimental Methods for Investigating Innovative Approaches to Nuclear Waste Management and to Nuclear Safety
Viebach, M., Knospe, A., Lange, C., Merk, B., & Hurtado, A. (2024). NAUTILUS: A Project for the Development of Experimental Methods for Investigating Innovative Approaches to Nuclear Waste Management and to Nuclear Safety. In International Conference on Physics of Reactors (PHYSOR 2024) (pp. 316-325). American Nuclear Society. doi:10.13182/physor24-43699
2023
New Waste Management Options Created by iMAGINE through Direct Operation on Spent Nuclear Fuel Feed
Merk, B., Detkina, A., Noori-kalkhoran, O., Jain, L., Litskevich, D., & Cartland-Glover, G. (n.d.). New Waste Management Options Created by iMAGINE through Direct Operation on Spent Nuclear Fuel Feed. Energies, 16(21), 7420. doi:10.3390/en16217420
New Waste Management Options Created by iMAGINE through Direct Operation on SNF Feed
Developing a Reactivity-Equivalent Physical Transformation to Simulate an Axially Heterogeneous Boiling Water Reactor
Mossop, R., Merk, B., Patel, M., Hino, T., & Peakman, A. (2023). Developing a Reactivity-Equivalent Physical Transformation to Simulate an Axially Heterogeneous Boiling Water Reactor. ENERGIES, 16(8). doi:10.3390/en16083359
iMAGINE-Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century
Merk, B., Litskevich, D., Detkina, A., Noori-kalkhoran, O., Jain, L., Derrer-Merk, E., . . . Cartland-Glover, G. (2023). iMAGINE-Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century. ENERGIES, 16(7). doi:10.3390/en16073120
iMAGINE – Visions, Missions, and Steps for Successfully Delivering the Nuclear System of the 21st Century
2022
A HELIOS-Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium-Based Initial Core for iMAGINE
Merk, B., Detkina, A., Litskevich, D., Noori-kalkhoran, O., Jain, L., & Cartland-Glover, G. (2022). A HELIOS-Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium-Based Initial Core for iMAGINE. Energies, 15(24), 9638. doi:10.3390/en15249638
On the Employment of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 1: Thermophysical Properties and Core Criticality
Noori-kalkhoran, O., Litskevich, D., Detkina, A., Jain, L., Cartland-Glover, G., & Merk, B. (2022). On the Employment of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 1: Thermophysical Properties and Core Criticality. ENERGIES, 15(23). doi:10.3390/en15238865
A HELIOS Based Dynamic Salt Clean-Up Study Analysing the Effects of a Plutonium Based Initial Core for IMAGINE
A First Step towards Zero Nuclear Waste-Advanced Strategic Thinking in Light of iMAGINE
Merk, B., Detkina, A., Litskevich, D., Patel, M., Noori-kalkhoran, O., Cartland-Glover, G., . . . Degueldre, C. (2022). A First Step towards Zero Nuclear Waste-Advanced Strategic Thinking in Light of iMAGINE. ENERGIES, 15(19). doi:10.3390/en15197209
A HELIOS-Based Dynamic Salt Clean-Up Study for iMAGINE
Merk, B., Detkina, A., Litskevich, D., Noori-Kalkhoran, O., & Cartland-Glover, G. (2022). A HELIOS-Based Dynamic Salt Clean-Up Study for iMAGINE. APPLIED SCIENCES-BASEL, 12(17). doi:10.3390/app12178748
A First Step to Zero Waste Nuclear – Advanced Strategic Thinking in the Light of iMAGINE
A HELIOS Based Dynamic Salt Clean-Up Study for iMAGINE
DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part II)
Davies, S., Litskevich, D., Merk, B., Levers, A., Bryce, P., & Detkina, A. (2022). DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part II). ENERGIES, 15(13). doi:10.3390/en15134843
Defining the Challenges-Identifying the Key Poisoning Elements to Be Separated in a Future Integrated Molten Salt Fast Reactor Clean-Up System for iMAGINE
Merk, B., Detkina, A., Litskevich, D., Drury, M., Noori-kalkhoran, O., Cartland-Glover, G., . . . Mount, A. R. (2022). Defining the Challenges-Identifying the Key Poisoning Elements to Be Separated in a Future Integrated Molten Salt Fast Reactor Clean-Up System for iMAGINE. APPLIED SCIENCES-BASEL, 12(9). doi:10.3390/app12094124
Defining the Challenges - Identifying the Key Poisoning Elements to be Separated in a Future Integrated Molten Salt Fast Reactor Clean-up System for iMAGINE
Merk, B., Detkina, A., Litskevich, D., Drury, M., Noorikalkhoran, O., Cartland-Glover, G., . . . Mount, A. (2022). Defining the Challenges - Identifying the Key Poisoning Elements to be Separated in a Future Integrated Molten Salt Fast Reactor Clean-up System for iMAGINE. doi:10.20944/preprints202202.0148.v1
Verification of the LOTUS Code with C5G7 Benchmark
Litskevich, D., Davies, S., Detkina, A., & Merk, B. (2022). Verification of the LOTUS Code with C5G7 Benchmark. In International Conference on Physics of Reactors 2022 (PHYSOR 2022) (pp. 1784-1791). American Nuclear Society. doi:10.13182/physor22-37729
Zero Power Experiment for Molten Salt Reactor -- Code Verification and Validation Request
Detkina, A., Litskevich, D., Drury, M., & Merk, B. (2022). Zero Power Experiment for Molten Salt Reactor -- Code Verification and Validation Request. In International Conference on Physics of Reactors 2022 (PHYSOR 2022) (pp. 998-1006). American Nuclear Society. doi:10.13182/physor22-37633
2021
DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)
Davies, S., Litskevich, D., Rohde, U., Detkina, A., Merk, B., Bryce, P., . . . Ravindra, V. (2021). DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I). ENERGIES, 14(16). doi:10.3390/en14165060
Evaluating Reactivity Control Options for a Chloride Salt-Based Molten Salt Zero-Power Reactor
Merk, B., Detkina, A., Atkinson, S., Litskevich, D., & Cartland-Glover, G. (2021). Evaluating Reactivity Control Options for a Chloride Salt-Based Molten Salt Zero-Power Reactor. APPLIED SCIENCES-BASEL, 11(16). doi:10.3390/app11167447
Innovative Investigation of Reflector Options for the Control of a Chloride-Based Molten Salt Zero-Power Reactor
Merk, B., Detkina, A., Atkinson, S., Litskevich, D., & Cartland-Glover, G. (n.d.). Innovative Investigation of Reflector Options for the Control of a Chloride-Based Molten Salt Zero-Power Reactor. Applied Sciences, 11(15), 6795. doi:10.3390/app11156795
On the Dimensions Required for a Molten Salt Zero Power Reactor Operating on Chloride Salts
Merk, B., Detkina, A., Atkinson, S., Litskevich, D., & Cartland-Glover, G. (n.d.). On the Dimensions Required for a Molten Salt Zero Power Reactor Operating on Chloride Salts. Applied Sciences, 11(15), 6673. doi:10.3390/app11156673
A Zero-power Facility as a Multi-fold Opportunity to Support Quick Progress in Innovative Reactor Developments
Merk, B., Litskevich, D., Detkina, A., Cartland-Glover, G., Atkinson, S., & Bankhead, M. (2021). A Zero-power Facility as a Multi-fold Opportunity to Support Quick Progress in Innovative Reactor Developments. atw - International Journal for Nuclear Power, 66(3), 59-64. Retrieved from https://www.kernd.de/kernd-en/fachzeitschrift-atw/
Part 3: Evaluating a small modular high temperature reactor design during control rod withdrawal and a depressurised loss of coolant accidents
Atkinson, S., Aoki, T., Litskevich, D., Merk, B., & Xing, Y. (2021). Part 3: Evaluating a small modular high temperature reactor design during control rod withdrawal and a depressurised loss of coolant accidents. Progress in Nuclear Energy, 134. doi:10.1016/j.pnucene.2021.103689
Assessment of High-Electrification UK Scenarios with Varying Levels of Nuclear Power and Associated Post-Fault Behaviour
Hadri, M., Trovato, V., Bialecki, A., Merk, B., & Peakman, A. (2021). Assessment of High-Electrification UK Scenarios with Varying Levels of Nuclear Power and Associated Post-Fault Behaviour. Energies, 14(6). doi:10.3390/en14061780
CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development
Davies, S., Rohde, U., Litskevich, D., Merk, B., Bryce, P., Levers, A., . . . Ravindra, V. (2021). CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development. ENERGIES, 14(5). doi:10.3390/en14051220
A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution
Atkinson, S., Detkina, A., Litskevich, D., & Merk, B. (n.d.). A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution. Energies, 14(4), 838. doi:10.3390/en14040838
Criticality Analysis for BWR Spent Fuel Based on the Burnup Credit Evaluation from Full Core Simulations
Detkina, A., Litskevitch, D., Peakman, A., & Merk, B. (n.d.). Criticality Analysis for BWR Spent Fuel Based on the Burnup Credit Evaluation from Full Core Simulations. Applied Sciences, 11(4), 1498. doi:10.3390/app11041498
A Zero-power Facility as a Multi-fold Opportunity to Support Quick Progress in Innovative Reactor Development
Merk, B., Litskevich, D., Detkina, A., Cartland-Glover, G., Atknison, S., & Bankhead, M. (2021). A Zero-power Facility as a Multi-fold Opportunity to Support Quick Progress in Innovative Reactor Development. ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 66(3), 59-64. Retrieved from https://www.webofscience.com/
2020
Burnup Credit Evaluation for BWR Spent Fuel from Full Core Calculations
Detkina, A., Litskevitch, D., Peakman, A., & Merk, B. (2020). Burnup Credit Evaluation for BWR Spent Fuel from Full Core Calculations. APPLIED SCIENCES-BASEL, 10(21). doi:10.3390/app10217549
Evaluation of BWR burnup calculations using deterministic lattice codes scale-6.2, WIMS-10A and CaSMO5
Detkina, A., Peakman, A., Litskevich, D., Liang, J. H., & Merk, B. (2020). Evaluation of BWR burnup calculations using deterministic lattice codes scale-6.2, WIMS-10A and CaSMO5. Energies, 13(10). doi:10.3390/en13102573
Verification of the current coupling collision probability method with orthogonal flux expansion for the case of single cell
Litskevich, D., Merk, B., & Atkinson, S. (2020). Verification of the current coupling collision probability method with orthogonal flux expansion for the case of single cell. PROGRESS IN NUCLEAR ENERGY, 120. doi:10.1016/j.pnucene.2019.103219
The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor
Merk, B., Detkina, A., Litskevich, D., Atkinson, S., & Cartland-Glover, G. (n.d.). The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor. Energies, 13(7), 1609. doi:10.3390/en13071609
The Potential of Pressurised Water Reactors to Provide Flexible Response in Future Electricity Grids
Peakman, A., Merk, B., & Hesketh, K. (2020). The Potential of Pressurised Water Reactors to Provide Flexible Response in Future Electricity Grids. ENERGIES, 13(4). doi:10.3390/en13040941
2019
Evaluation of the Breeding Performance of a NaCl-UCl-Based Reactor System
Merk, B., Detkina, A., Atkinson, S., Litskevich, D., & Cartland-Glover, G. (2019). Evaluation of the Breeding Performance of a NaCl-UCl-Based Reactor System. ENERGIES, 12(20). doi:10.3390/en12203853
The Role of Nuclear Power in Meeting Current and Future Industrial Process Heat Demands
Peakman, A., & Merk, B. (2019). The Role of Nuclear Power in Meeting Current and Future Industrial Process Heat Demands. ENERGIES, 12(19). doi:10.3390/en12193664
On the numerical modelling of frozen walls in a molten salt fast reactor
Cartland Glover, G., Skillen, A., Litskevich, D., Rolfo, S., Emerson, D. R., Merk, B., & Moulinec, C. (2019). On the numerical modelling of frozen walls in a molten salt fast reactor. Nuclear Engineering and Design, 355. doi:10.1016/j.nucengdes.2019.110290
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?
Merk, B., Litskevich, D., Peakman, A., & Bankhead, M. (2019). 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?. ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 64(6-7), 353-359. Retrieved from http://gateway.webofknowledge.com/
The Current Status of Partitioning & Transmutation and How to Develop a Vision for Nuclear Waste Management
Merk, B., Litskevich, D., Peakman, A., & Bankhead, M. (2019). The Current Status of Partitioning & Transmutation and How to Develop a Vision for Nuclear Waste Management. ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 64(5), 261-266. Retrieved from https://www.webofscience.com/
Small modular high temperature reactor optimisation - Part 1: A comparison between beryllium oxide and nuclear graphite in a small scale high temperature reactor
Atkinson, S., Abram, T. J., Litskevich, D., & Merk, B. (2019). Small modular high temperature reactor optimisation - Part 1: A comparison between beryllium oxide and nuclear graphite in a small scale high temperature reactor. PROGRESS IN NUCLEAR ENERGY, 111, 223-232. doi:10.1016/j.pnucene.2018.10.017
Small modular high temperature reactor optimisation part 2: Reactivity control for prismatic core high temperature small modular reactor, including fixed burnable poisons, spectrum hardening and control rods
Atkinson, S., Litskevich, D., & Merk, B. (2019). Small modular high temperature reactor optimisation part 2: Reactivity control for prismatic core high temperature small modular reactor, including fixed burnable poisons, spectrum hardening and control rods. PROGRESS IN NUCLEAR ENERGY, 111, 233-242. doi:10.1016/j.pnucene.2018.11.001
Modelling the draining of a molten chloride salt reactor
Lewis, E., Cartland-Glover, G., Rolfo, S., Moulinec, C., Emerson, D. R., & Merk, B. (2019). Modelling the draining of a molten chloride salt reactor. In 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 (pp. 4470-4483).
Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects
Brovchenko, M., Kloosterman, J. -L., Luzzi, L., Merle, E., Heuer, D., Laureau, A., . . . Merk, B. (2019). Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects. EPJ Nuclear Sciences & Technologies, 5, 2. doi:10.1051/epjn/2018052
2018
On a roadmap for future industrial nuclear reactor core simulation in the U.K. to support the nuclear renaissance
Merk, B., Bankhead, M., Litskevich, D., Gregg, R., Peakman, A., & Shearer, C. (2018). On a roadmap for future industrial nuclear reactor core simulation in the U.K. to support the nuclear renaissance. Energies, 11(12). doi:10.3390/en11123509
A disruptive approach to eliminating weapongrade plutonium - Pu burning in a molten salt fast reactor
Merk, B., & Litskevich, D. (2018). A disruptive approach to eliminating weapongrade plutonium - Pu burning in a molten salt fast reactor. PLOS ONE, 13(8). doi:10.1371/journal.pone.0201757
Advanced micro-reactor concepts
Peakman, A., Hodgson, Z., & Merk, B. (2018). Advanced micro-reactor concepts. PROGRESS IN NUCLEAR ENERGY, 107, 61-70. doi:10.1016/j.pnucene.2018.02.025
MODELLING AND SIMULATION ACTIVITIES IN SUPPORT OF THE UK NUCLEAR R&D PROGRAMME ON DIGITAL REACTOR DESIGN
Lindley, B., Allen, D., Lillington, J., Smethurst, A., Smith, P., Bowman, D., . . . Eaton, M. D. (2018). MODELLING AND SIMULATION ACTIVITIES IN SUPPORT OF THE UK NUCLEAR R&D PROGRAMME ON DIGITAL REACTOR DESIGN. In PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 3. Retrieved from https://www.webofscience.com/
MODELLING FROZEN SALT FILMS IN A MOLTEN SALT FAST REACTOR
Cartland-Glover, G. M., Rolfo, S., Skillen, A., Emerson, D. R., Moulinec, C., Litskevich, D., & Merk, B. (2018). MODELLING FROZEN SALT FILMS IN A MOLTEN SALT FAST REACTOR. In PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 8. Retrieved from https://www.webofscience.com/
MODELLING THE NEUTRONICS OF A MOLTEN SALT FAST REACTOR USING DYN3D-MG FOR THE INVESTIGATION OF THE APPLICATION OF FROZEN WALL TECHNOLOGY
Cartland-Glover, G. M., Rolfo, S., Skillen, A., Emerson, D. R., Moulinec, C., Litskevich, D., & Merk, B. (2018). MODELLING THE NEUTRONICS OF A MOLTEN SALT FAST REACTOR USING DYN3D-MG FOR THE INVESTIGATION OF THE APPLICATION OF FROZEN WALL TECHNOLOGY. In PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 5. Retrieved from https://www.webofscience.com/
Demand driven salt clean-up in a molten salt fast reactor - Defining a priority list
Merk, B., Litskevich, D., Gregg, R., & Mount, A. R. (2018). Demand driven salt clean-up in a molten salt fast reactor - Defining a priority list. PLOS ONE, 13(3). doi:10.1371/journal.pone.0192020
Nuclear waste = fuel of the future?
Merk, B. (n.d.). Nuclear waste = fuel of the future?. Science Journal for Kids.
The UK nuclear R&D programme on digital nuclear reactor design - modelling, simulation, and virtual engineering
Merk, B., Allen, D., Bankhead, M., Bowen, A., Bowman, D., De Haas, S., . . . Vikhorev, K. (2018). The UK nuclear R&D programme on digital nuclear reactor design - modelling, simulation, and virtual engineering. In Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 (pp. 1085-1090).
Variable Reactivity Control in Small Modular High Temperature Reactors Using Moderation Manipulation Techniques
Atkinson, S., Litskevich, D., & Merk, B. (2018). Variable Reactivity Control in Small Modular High Temperature Reactors Using Moderation Manipulation Techniques. ENERGIES, 11(7). doi:10.3390/en11071897
2017
An innovative way of thinking nuclear waste management - Neutron physics of a reactor directly operating on SNF
Merk, B., Litskevich, D., Bankhead, M., & Taylor, R. J. (2017). An innovative way of thinking nuclear waste management - Neutron physics of a reactor directly operating on SNF. PLOS ONE, 12(7). doi:10.1371/journal.pone.0180703
Can enhanced feedback effects and improved breeding coincide in a metal fueled, sodium cooled fast reactor?
Merk, B., Devan, K., Bachchan, A., Paul, D., Puthiyavinayagam, P., & Srinivasan, G. (2017). Can enhanced feedback effects and improved breeding coincide in a metal fueled, sodium cooled fast reactor?. ANNALS OF NUCLEAR ENERGY, 105, 205-218. doi:10.1016/j.anucene.2017.03.018
On a Long Term Strategy for the Success of Nuclear Power
Merk, B., Litskevich, D., Whittle, K. R., Bankhead, M., Taylor, R. J., & Mathers, D. (2017). On a Long Term Strategy for the Success of Nuclear Power. Energies, 10(7), 867. doi:10.3390/en10070867
On a Long Term Strategy for the Success of Nuclear Power
The UK national program R&D on digital nuclear reactor design
Merk, B., Bankhead, M., Dwyer, L., & Bowen, A. (2017). The UK national program R&D on digital nuclear reactor design. In Transactions of the American Nuclear Society Vol. 117 (pp. 1328-1330).
2016
Partitioning and Transmutation of Transuranium Elements Under Nuclear Phase-out Conditions - technically Reliable?
Merk, B., & Rohde, U. (2016). Partitioning and Transmutation of Transuranium Elements Under Nuclear Phase-out Conditions - technically Reliable?. ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 61(4), 259-+. Retrieved from https://www.webofscience.com/
A molten salt reactor study for the transmutation of all German transuranium in the frame of the nuclear phase out
Merk, B., & Litskevich, D. (2016). A molten salt reactor study for the transmutation of all German transuranium in the frame of the nuclear phase out. In Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century Vol. 5 (pp. 3107-3116).
Evaluation of the safety and breeding performance of a heterogeneous fuel assembly design for a metal fueled SFR
Merk, B., Devan, K., Puthiyavinayagam, P., Bachchan, A., Paul, D., & Srinivasan, G. (2016). Evaluation of the safety and breeding performance of a heterogeneous fuel assembly design for a metal fueled SFR. In Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century Vol. 5 (pp. 3094-3106).
2015
Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?
Merk, B., & Litskevich, D. (2015). Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?. PLOS ONE, 10(12). doi:10.1371/journal.pone.0145652
On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor-A Neutron Physical Study
Merk, B., & Litskevich, D. (2015). On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor-A Neutron Physical Study. ENERGIES, 8(11), 12557-12572. doi:10.3390/en81112328
On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study
Merk, B., & Litskevich, D. (2015). On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study. Energies, 8(11), 12328.
Progress in reliability of fast reactor operation and new trends to increased inherent safety
Merk, B., Stanculescu, A., Chellapandi, P., & Hill, R. (2015). Progress in reliability of fast reactor operation and new trends to increased inherent safety. Applied Energy, 147, 104-116. doi:10.1016/j.apenergy.2015.02.023
Current coupling collision probability method with orthonormal flux expansion for unstructured geometries
Litskevich, D., & Merk, B. (2015). Current coupling collision probability method with orthonormal flux expansion for unstructured geometries. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015 Vol. 4 (pp. 2867-2880).
2014
SP3 Solution versus Diffusion Solution in Pin-by-Pin Calculations and Conclusions Concerning Advanced Methods
Litskevich, D., & Merk, B. (2014). SP3 Solution versus Diffusion Solution in Pin-by-Pin Calculations and Conclusions Concerning Advanced Methods. JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT, 43(1-7), 214-239. doi:10.1080/00411450.2014.913184
Simulation of thermal fluid dynamics in parabolic trough receiver tubes with direct steam generation using the computer code ATHLET
Hoffmann, A., Merk, B., Hirsch, T., & Pitz-Paal, R. (2014). Simulation of thermal fluid dynamics in parabolic trough receiver tubes with direct steam generation using the computer code ATHLET. Kerntechnik, 79(3), 175-186. doi:10.3139/124.110419
On the Use of a Molten Salt Fast Reactor to Apply an Idealized Transmutation Scenario for the Nuclear Phase Out
Merk, B., Rohde, U., Glivici-Cotruta, V., Litskevich, D., & Scholl, S. (2014). On the Use of a Molten Salt Fast Reactor to Apply an Idealized Transmutation Scenario for the Nuclear Phase Out. PLOS ONE, 9(4). doi:10.1371/journal.pone.0092776
Neutron shielding studies on an advanced molten salt fast reactor design
Merk, B., & Konheiser, J. (2014). Neutron shielding studies on an advanced molten salt fast reactor design. Annals of Nuclear Energy, 64, 441-448. doi:10.1016/j.anucene.2013.07.014
2013
Overview of major HZDR developments for fast reactor analysis
Merk, B., Glivici-Cotruţă, V., Duerigen, S., Rohde, U., & Kliem, S. (2013). Overview of major HZDR developments for fast reactor analysis. Nuclear Engineering and Design, 265, 1194-1204. doi:10.1016/j.nucengdes.2013.07.026
Fine Distributed Moderating Material with Improved Thermal Stability Applied to Enhance the Feedback Effects in SFR Cores
Merk, B. (2013). Fine Distributed Moderating Material with Improved Thermal Stability Applied to Enhance the Feedback Effects in SFR Cores. Science and Technology of Nuclear Installations, 2013, 1-11. doi:10.1155/2013/217548
Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores
Merk, B. (2013). Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores. Science and Technology of Nuclear Installations, 2013, 1-10. doi:10.1155/2013/172518
2012
An Analytical Solution of the Time-Dependent Diffusion Equation in a Composite Slab
Glivici-Cotruţă, V., & Merk, B. (2012). An Analytical Solution of the Time-Dependent Diffusion Equation in a Composite Slab. Transport Theory and Statistical Physics, 41(5-6), 356-367. doi:10.1080/00411450.2012.671217
Development and verification of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
Rohde, U., Baier, S., Duerigen, S., Fridman, E., Kliem, S., & Merk, B. (2012). Development and verification of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR. Nuclear Engineering and Design, 251, 412-422. doi:10.1016/j.nucengdes.2011.09.051
An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies
Merk, B., & Rohde, U. (2012). An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies. Kerntechnik, 77(4), 230-239. doi:10.3139/124.110248
On the use of different analytical solutions for recalculation of the YALINA-Booster experiment SC3A
Merk, B., Glivici-Cotruţă, V., & Weiß, F. P. (2012). On the use of different analytical solutions for recalculation of the YALINA-Booster experiment SC3A. Progress in Nuclear Energy, 58, 11-20. doi:10.1016/j.pnucene.2012.01.001
Use of Zirconium-Based Moderators to Enhance Feedback Coefficients in a MOX-Fueled Sodium-Cooled Fast Reactor
Merk, B., Kliem, S., Fridman, E., & Weiss, F. -P. (2012). Use of Zirconium-Based Moderators to Enhance Feedback Coefficients in a MOX-Fueled Sodium-Cooled Fast Reactor. Nuclear Science and Engineering, 171(2), 136-149. doi:10.13182/nse10-58
Solutions without Space-Time Separation for ADS Experiments: Overview on Developments and Applications
Merk, B., & Glivici-Cotruţă, V. (2012). Solutions without Space-Time Separation for ADS Experiments: Overview on Developments and Applications. Science and Technology of Nuclear Installations, 2012, 1-11. doi:10.1155/2012/140946
2011
An analytical solution for the consideration of the effect of adjacent fuel elements
Merk, B., & Rohde, U. (2011). An analytical solution for the consideration of the effect of adjacent fuel elements. Annals of Nuclear Energy, 38(11), 2428-2440. doi:10.1016/j.anucene.2011.07.003
Analysis of the influence of different arrangements for ZrH moderator material on the performance of a SFR core
Merk, B., & Weiß, F. -P. (2011). Analysis of the influence of different arrangements for ZrH moderator material on the performance of a SFR core. Annals of Nuclear Energy, 38(11), 2374-2385. doi:10.1016/j.anucene.2011.07.005
Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
Rohde, U., Baier, S., Duerigen, S., Fridman, E., Kliem, S., & Merk, B. (2011). Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR. Kerntechnik, 76(3), 166-173. doi:10.3139/124.110147
On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors
Merk, B., Fridman, E., & Weiß, F. -P. (2011). On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors. Annals of Nuclear Energy, 38(5), 921-929. doi:10.1016/j.anucene.2011.01.024
2010
A two group analytical approximation solution for an external source problem without separation of space and time
Merk, B., & Weiß, F. P. (2010). A two group analytical approximation solution for an external source problem without separation of space and time. Annals of Nuclear Energy, 37(7), 942-952. doi:10.1016/j.anucene.2010.03.011
2009
A Three-Scale Expansion Solution for a Time-Dependent<i>P<sub>1</sub></i>Neutron Transport Problem with External Source
Merk, B., & Weiß, F. P. (2009). A Three-Scale Expansion Solution for a Time-Dependent<i>P<sub>1</sub></i>Neutron Transport Problem with External Source. Nuclear Science and Engineering, 163(2), 152-174. doi:10.13182/nse163-152
On the influence of spatial discretization in LWR-burnup calculations with HELIOS 1.9 – Part I: Uranium oxide (UOX) fuel
Merk, B. (2009). On the influence of spatial discretization in LWR-burnup calculations with HELIOS 1.9 – Part I: Uranium oxide (UOX) fuel. Annals of Nuclear Energy, 36(2), 151-167. doi:10.1016/j.anucene.2008.11.020
On the influence of spatial discretization in LWR-burnup calculations with HELIOS 1.9 – Part II: Mixed oxide (MOX) fuel
Merk, B. (2009). On the influence of spatial discretization in LWR-burnup calculations with HELIOS 1.9 – Part II: Mixed oxide (MOX) fuel. Annals of Nuclear Energy, 36(2), 168-182. doi:10.1016/j.anucene.2008.11.019
An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production
Merk, B. (2009). An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production. Nuclear Science and Engineering, 161(1), 49-67. doi:10.13182/nse161-49
2008
An Analytical Solution for a One Dimensional Time-Dependent Neutron Transport Problem with External Source
Merk, B. (2008). An Analytical Solution for a One Dimensional Time-Dependent Neutron Transport Problem with External Source. Transport Theory and Statistical Physics, 37(5-7), 535-549. doi:10.1080/00411450802526327
On the influence of spatial discretization in LWR cell- and lattice calculations with HELIOS 1.9
Merk, B., & Koch, R. (2008). On the influence of spatial discretization in LWR cell- and lattice calculations with HELIOS 1.9. Annals of Nuclear Energy, 35(8), 1492-1501. doi:10.1016/j.anucene.2008.01.022