Introduction ***** How Does CONFLUX Work? ====================== The CONFLUX (Calculation Of Neutrino FLUX) software framework is built with the goal to simplify and standardize neutrino flux calculations. CONFLUX is packaged with three prediction modes: - Summation mode - :math:`\beta` Conversion mode - Direct neutrino data mode CONFLUX uses parsered nuclear data, theoretical beta/neutrino spectrum calclation, and existing beta/neutrino measurement from fissile isotopes to calculate reactor or beta decay neutrino productions. The full documentation has been published in BLAH. .. image:: block_diagram.jpg CONFLUX was built aiming to help researchers with limited programming and nuclear data knowledge to calculate neutrino flux with ease. Features include: - Calculating neutrino spectrum and flux from customized model of nuclear reactor - Beta and neutrino spectrum with non-zero neutrino mass - Allow user input of covariance matrix among fission product yields - Neutrino flux evolution over time from independent fission yields - Calculating neutrino flux with customized beta decay function, updated nuclear data, or individually modified isotopic data Modes ===== Summation --------- Summation mode is an ab-initio calculation that takes in Fission product information, either from ``ENDF``, ``JEFF``, or a ``user-defined DB``, and combines it with the spectral shape of each individual :math:`\beta`-branch. Thus, we sum the product of the individual branch spectra and their contributions to form the total neutrino spectrum for a given isotope. A block diagram of how the mode works, as well as a graphical representation of the calculation is provided below. .. image:: Summation_block.jpg .. image:: Summation_figure.png Conversion ---------- Conversion mode converts an inputted beta spectrum of some fissile isotope and converts it into a neutrino spectrum by fitting it with ``virtual branches`` that approximate neutrino decay branches. Packaged beta databases lack corrections for non-equilibrium fission products, however one can use the Summation calculation with prior knowledge of the modeled reactor to work around this. See also ``synth_data.py``. A block diagram of how the mode works, as well as a graphical representation of the calculation is provided below. .. image:: Conversion_block.jpg .. image:: Conversion_figure.png Direct Experimental Measurement ------------------------------- This is a planned prediction mode that will be implemented at a later date. More on how the calculation will be carried out can be seen here_. .. _here: https://journals.aps.org/prl/abstract/10.1103/PhysRevLett.128.081801 Databases ========= ENDF/JEFF --------- ENDF and JEFF are Nuclear Databases containing Fission Yields of Individual Fission Isotopes. Either can be selected in the calculation by specificying which Database in the ``Default_DB`` variable where required. Some key notes on the parsed data include - HEAD AWR - FissionZA : This is an identifier for this specific Isotope, combining both its' atomic number and mass. - LE - MT : Determines whether that specific set of data is an Indpendant Yield ``IFP`` or a Cumulative Yield ``CFP`` - Ei : This is the incident neutron energy that causes the fission. Value can either be 0 (thermal), 0.5 (fast), or 14 (relativistic) - Ii - NFPI .. literalinclude:: ENDF_example.txt ENSDF ----- .. literalinclude:: ENSDF_example.txt FyCOM ----- Prepackaged example covariance and correlation matrices are included for the fission products from U-235, U-238, Pu-239, and Pu-241, calculated by the work referred in https://nucleardata.berkeley.edu/FYCoM/, a MC calculation based on ENDF.B/VIII and JEFF-3.3. The user can download the referred covariance matrices by running .. code-block:: bash python3 $CONFLUX_DB/CovMatDownloader.py Conversion Libraries -------------------- Beta Spectrum Generator =======================