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Title: Cross-section generation methodology for three-dimensional transient reactor simulation

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:552456
; ; ;  [1]
  1. Pennsylvania State Univ., University Park, PA (United States)

An important aspect of three-dimensional transient reactor calculations is the cross-section modeling algorithm. Based on our experience in transient simulations of different accident scenarios with Pennsylvania State University`s coupled code TRAC-PF1/NEM, an original cross-section generation methodology was developed and tested. Well-known features were combined with new developments to achieve an accurate and efficient coupled three-dimensional kinetics/thermal-hydraulic system modeling. Our approach is designed to describe both initial steady state and the entire range of conditions expected during a transient. It differs from the existing cross-section generation procedures in both history and instantaneous models.

OSTI ID:
552456
Report Number(s):
CONF-971125-; ISSN 0003-018X; TRN: 98:001666
Journal Information:
Transactions of the American Nuclear Society, Vol. 77; Conference: 1997 American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997; Other Information: PBD: 1997
Country of Publication:
United States
Language:
English