CASMO

CASMO-5 development and applications. CASMO-5 is the latest code version in the Studsvik Scandpower series of lattice physics codes for general LWR analysis and has capabilities, features and numerical models not previously available in CASMO-4. Among the new capabilities of CASMO-5 are a ”quadratic gadolinium depletion model” and the ability to perform 2D transport calculations in hundreds of energy groups. This paper briefly describes CASMO-5 capabilities and the role of CASMO-5 in generating cross section and discontinuity factor data for SIMULATE-4. This paper also describes the new CASMO-5 data libraries (586 group neutron and 18 group gamma), and details recent work to validate CASMO-5 2D transport calculations for several simple criticals.


References in zbMATH (referenced in 10 articles )

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  1. Park, H.; Chacón, L.; Matsekh, A.; Chen, G.: A multigroup moment-accelerated deterministic particle solver for 1-D time-dependent thermal radiative transfer problems (2019)
  2. Josey, C.; Forget, B.; Smith, K.: High order methods for the integration of the Bateman equations and other problems of the form of (y^\prime=F(y,t)y) (2017)
  3. Kochunas, Brendan; Fitzgerald, Andrew; Larsen, Edward: Fourier analysis of iteration schemes for (k)-eigenvalue transport problems with flux-dependent cross sections (2017)
  4. Keady, Kendra P.; Larsen, Edward W.: Stability of Monte Carlo (k)-eigenvalue simulations with CMFD feedback (2016)
  5. Choi, Sooyoung; Smith, Kord; Lee, Hyun Chul; Lee, Deokjung: Impact of inflow transport approximation on light water reactor analysis (2015)
  6. Densmore, J. D.; Park, H.; Wollaber, A. B.; Rauenzahn, R. M.; Knoll, D. A.: Monte Carlo simulation methods in moment-based scale-bridging algorithms for thermal radiative-transfer problems (2015)
  7. Jeong, Yongjin; Park, Jinsu; Lee, Hyun Chul; Lee, Deokjung: Convergence analysis of two-node CMFD method for two-group neutron diffusion eigenvalue problem (2015)
  8. Roberts, Jeremy A.; Forget, Benoit: Multigroup diffusion preconditioners for multiplying fixed-source transport problems (2014)
  9. Willert, Jeffrey; Park, H.; Knoll, D. A.: A comparison of acceleration methods for solving the neutron transport (k) -eigenvalue problem (2014)
  10. Park, H.; Knoll, D. A.; Rauenzahn, R. M.; Wollaber, A. B.; Densmore, J. D.: A consistent, moment-based, multiscale solution approach for thermal radiative transfer problems (2012)