Publications
2024
Evaluating the Impact of Neutron Absorber Materials on Spent Fuel Pool Rack Criticality Using OpenMC Monte Carlo Code
Buyrukcu, B., Buyrukcu, E., Litskevich, D., & Whittle, K. (2024). Evaluating the Impact of Neutron Absorber Materials on Spent Fuel Pool Rack Criticality Using OpenMC Monte Carlo Code. In Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle. American Society of Mechanical Engineers. doi:10.1115/icone31-137004
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
A Draft Design of a Zero Power Experiment for Molten Salt Fast Reactor Studies
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
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
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
Verification of the current coupling collision probability method with orthogonal flux expansion for the assembly calculations
Litskevich, D., Atkinson, S., & Davies, S. (2020). Verification of the current coupling collision probability method with orthogonal flux expansion for the assembly calculations. Progress in Nuclear Energy, 130, 103562. doi:10.1016/j.pnucene.2020.103562
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
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
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
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
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
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
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
2016
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).
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.
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
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