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Impact of spectral history effects on PWR core analysis

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:411766
 [1];  [2]
  1. Studsvik Company, Newton Centre, MA (United States)
  2. Studsvik of America, Idaho Falls, ID (United States)
The accuracy of pressurized water reactor (PWR) core analyses depends on the spatial resolution of the core neutronics model, as well as the accuracy of the cross-section data used in the core model. The spatial accuracy of modern advanced nodal core models has been well established by many researchers. However, the accuracy of cross-section models has received decidedly less attention, and their accuracy is difficult to assess. The complexity of the cross-section models arises from the fact that there are many discrete sources of approximation: (1) source of fundamental nuclear data (e.g., ENDF-B/VI, JEF-2, JENDL-3, etc.), (2) lattice physics code used for assembly calculations (e.g., CASMO-4, PHOENIX, DIT, etc.), (3) matrix of assembly depletion/branch calculations cases (e.g., number of temperature branches), (4) method used to fit/interpolate depletion/branch case data (e.g., polynomials or three-dimensional tables), (5) nodal code model used to treat assembly homogenization (e.g., discontinuity factors), (6) nodal code model used for depletion effects (e.g., microscopic or macroscopic depletion), (7) nodal code model used to treat intranodal depletion effects (e.g., burnup distributions), and (8) nodal code model used to treat intranodal instantaneous effects (e.g., spectrum/leakage).
OSTI ID:
411766
Report Number(s):
CONF-951006--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English

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