The two-dimensional transport solution within CASMO-4
- Studsvik Company, Newton Centre, MA (United States)
First-generation lattice physics codes, such as CASMO-1 through CASMO-3 (Ref. 1), were developed in an effort to analyze relatively short fuel cycles of [approximately]12 months. Fuel designs for these cycles were only mildly heterogeneous, containing a narrow range of enrichments and small loadings of burnable absorbers. The transport methods in these earlier codes, such as transmission probabilities for homogeneous cells, were more than adequate for such fuel designs. As utilities strive for longer cycle lengths, fuel designs have become far more heterogeneous, The current generation of boiling water reactor (BWR) fuel designs may contain nearly 100 fuel pins, with enrichments ranging from 2 to 5% and gadolinia loadings upward of 10% in as many as a dozen pins. In addition, these designs contain large islands of water in and around the center of the assembly and varying amounts of box wall material around the corners of the channel. Such heterogeneities require a more accurate representation at the level of the two-dimensional transport calculation, and this need has fueled interest in a new generation of lattice physics codes. In the most recent version of CASMO (i.e., CASMO-4), the two-dimensional homogeneous transmission probability module from earlier CASMO versions has been replaced with a heterogeneous characteristics solution. Although not entirely integral in nature, the characteristics method combines the most desirable features of integral transport theory (i.e., heterogeneous geometry, explicit representation of streaming, and the capability of generating an exact solution for a given set of data) with those of discrete ordinates (i.e., easy representation of anisotropic scattering and execution time that is directly proportional to problem size).
- OSTI ID:
- 5715735
- Report Number(s):
- CONF-930601-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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