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Reactors designed by Argonne National Laboratory


DYMOND (Fuel Cycle Transition Analysis Codes)


Standard Code Description

  1. Name of Program:
    DYMOND (Dynamic Model of Nuclear Deployment) Version 6DYMOND
  1. Computer for Which Program is Designed and Other Machine Version Packages Available:
    Designed to operate on Windows 10, though it functions on any workstation that can run Java (Linux, Mac, Windows). Developed using AnyLogic modeling platform. Requires access to ORIGEN-2 (and ORIGEN-S for future versions).
  2. Description of Problem or Function:
    DYMOND is a nuclear fuel cycle systems code that simulates the time-dependent behavior and evolution of the entire nuclear fuel cycle including mining, enrichment, fueling, reactors, reprocessing, waste management, disposal, etc. It utilizes a hybrid approach of using agents-based modeling for reactors and fuel batches and system dynamics-based modeling for fuel cycle processes. Given user-specified information about the nuclear fleet and deployment or transition scenario (simulation duration, initial reactors, reactor retirement profile, energy demand, available reactor and fuel technologies, recycling strategies, reactor deployment and fuel use priorities, etc.), DYMOND will calculate the amount of reactors and facilities constructed and retired and all fuel cycle mass flows at each time step to reveal any facility or resource bottlenecks, shortfalls, and surpluses, as well as inventories of materials in storage. The ORIGEN code is called directly by DYMOND to perform depletion calculations of each fuel batch to provide the detailed isotopics at discharge and after a cooling period that includes radioactive decay. ORIGEN is also used for the fuel loading model, which calculates the required fissile content of fresh fuel based on the isotopics of the feed material.
  3. Restrictions on the Complexity of the Problems:
    DYMOND currently allows for a maximum of 5 reactor types with up to 5 fuel batches per core and 3 reprocessing plant types. The simulation can also at most be 300 total years in simulated time. Also, all attributes of a reactor type or reprocessing type (power, capacity factor, final burnup, total capacity, etc.) are fixed for a simulation but there are input strategies to circumvent this restriction.
  4. Typical Running Time:
    Run times are highly variable depending on the simulation input. With fuel depletion modeled using ORIGEN-2, and using the burnup search option for the fuel loading, a 300-year simulation with 50 active reactors takes approximately 5 hours running on Windows 10.  However, a simulation with 10 active reactors and using the Pu-239 equivalence model for fuel loading will result in run times closer to 1.5 hours.
  5. Unusual Features of the Program:
    Ability to perform a direct burnup calculation for each fuel mixture to determine the required fuel composition.
  6. Related and Auxiliary Programs:
    Currently coupled to DAKOTA via Python for sensitivity analyses and uncertainty quantification.
  7. Status:
    Currently in development mode. Future versions will be developed and made available.
  8. References:
    1. H. Thierry, C. Senac, and B. Feng, “DYMOND 6 User Manual,” Argonne National Laboratory (2019).
  9. Machine Requirements:
    Operating system that can run Java SDK 12.0 or newer.
  10. Programming Languages Used:
    Java. Future versions with ORIGEN-S will include C++ for coupling interface.
  11. Operating System:
    No special requirements are made on the operating system. Windows/Linux/MacOS
  12. Other Programming or Operating Information or Restrictions:
  13. Name and Establishment of Author or Contributor:
    • Bo Feng, Argonne National Laboratory
  14. Materials Available:
    Future public release will be available..
  15. Sponsor:
    U.S. Department of Energy, Office of Nuclear Energy

Last Modified: Thu, June 11, 2020 9:41 AM



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