GAMSOR: Gamma Source Preparation and DIF3D Flux Solution

Abstract

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Verification of the MC2-3 Gamma Library

“…Simple 2D and 1D problems were constructed based on fast reactor compositions to verify the gamma library and calculation using MC 2 -3/DIF3D/GAMSOR (hereafter DIF3D represents DIF3D-VARIANT). For 2D problems [6], two configurations were set up based upon a simple 2D. One is a uranium dominated core region in the core region with the control rod inserted in the outer core region (case 1), as shown in Figure 3-6.…”

“…With the new gamma library, attempts were made to verify the neutron and gamma heating data for individual isotopes and to solve the EBR-II 138B benchmark problem again to confirm the previous calculation results and compare solution accuracies between the current and new libraries. In addition, the 2D benchmark problem discussed in the GAMSOR manual [6] was revisited since noticeable errors in gamma heatings in the non-fuel regions were reported in the document. For further investigation, simpler 1D benchmark problems were devised to compare neutron and gamma heating between MC 2 -3/DIF3D/GAMSOR and MCNP, in which no contribution of delayed gamma and betas were considered for the consistent comparison.…”

Argonne Reactor Code Software Verification and Validation Plan for the Versatile Test Reactor

“…The REBUS software uses the DIF3D software at each time step of the fuel cycle to obtain the steady state neutron flux solution and has a very specific methodology about how the flux solution changes over the time step to produce the correct fuel transmutation. The REBUS software provides a snapshot of the reactor state at each time point which can be used to define the input for GAMSOR software [8]. GAMSOR is a wrapper around the DIF3D software to allow the user to compute the coupled neutron-gamma transport calculation and produce both neutron and gamma heating throughout the modeled reactor system.…”

“…This document discusses the intended software verification and validation plan for the Argonne Reactor Code (ARC) software package [1][2][3][4][5][6][7][8][9][10][11][12][13] as part of the Versatile Test Reactor (VTR) program. The ARC software package consists of steady state neutronics and thermal hydraulics modeling capabilities which are being used by the VTR program to develop most of the VTR reactor design details which will be part of the licensing application.…”

Status of the NEAMS and ARC neutronic fast reactor tools integration to the NEAMS Workbench

“…The current focus of the Workbench integration is on the deterministic neutronic codes. It includes MC2-3 [6] for multi-group cross-section processing, DIF3D [7] for flux calculation, REBUS-3 [8] for depletion and equilibrium calculations, PERSENT [9] for perturbation theory calculations (perturbation, sensitivity and uncertainty quantification), and GAMSOR [10] for gamma heating calculations. These ARC codes are used at national laboratories, universities, and companies for advanced reactor analyses.…”