Physics Modelling and Verification

Neutron Transport and Cross Sections

GUARDYAN uses the cross section data table ENDF/B-VII.1 in ACE (A Compact ENDF) format. Interaction sampling follows similar techniques as in MCNP and OpenMC (​OpenMC). Albeit not optimal for GPU applications, we have chosen the already paved way in order to create an easily verifiable code. Major efficiency gain is expected from transforming interaction sampling towards eliminating rejection steps even in exchange for particle weight change: the latter being disadvantageous for the statistical variance the former minimizing thread divergence.

Free path sampling follows the Woodcock (delta-tracking) scheme with energy dependent majorant sampling cross section. The selection of isotope and interaction type happens in the analog way except for choosing between scattering and fission events.

We consider reactions with the following MT numbers: 2, 5, 11, 16, 17, 18, 19, 20, 21, 22, 23, 24, 25, 28, 29, 30, 32, 33, 34, 35, 36, 37, 38, 41, 44, 45, 51-90, 101. After choosing the reaction, the determination of the new energy and angle of the neutron depends on the given ACE law (ACE Laws 3, 4, 7, 9, 11, 44, 61 or 66 ). S(alpha, beta) treatment and handling unresolved resonances are not yet included in the physics modeling.

Verification

Often a verification of a newly implemented reactor physics code is done in an integral sense, on a near critical assembly with complicated geometry and the estimation of integral parameters like the k_eff is compared to a well established code calculation result. As GUARDYAN is meant primarily to simulate time evolution of power level and flux we have decided to compare time and energy spectra separately for a broad selection of isotopes. A small subcritical model was also created for validating geometry features and isotope mixture handling.

The verification basic model was a sphere containing a single isotope with density belonging to the natural isotope abundance. Neutrons were started at time zero. In separate calculations 5 starting energies were selected: 10^-8, 10^-6, 10^-3, 1, 18 MeV thereby the interaction types for the full relevant energy range (from thermal up to the energy limit of commonly available cross section data). For each isotope the radius of the sphere was set to three times the free path length at the neutron starting energy. First GUARDYAN was executed and the particles registered at the outer bounding surface of the sphere. Next, using smallest and largest values of energy and time of the GUARDYAN samples a tally bin structure is set up with 24 logarithmic energy bins and 9 equally spaced time bins. MCNP6 input was generated and executed with these tally settings.

The list of isotopes includes every isotope present in ENDF/B-VII.1, except for the metastable ones.

The subcritical model was a 30 cm radius water sphere with 61 UO₂ cylindrical fuel rods of 40 cm length, 1 cm radius spaced 1 cm apart from each other see figure. Uranium was 4.7% enriched and fuel rod density was taken as 10.5g/cm³.

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