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Abstract

This publication concerns the application of the new generation of thermal-hydraulic codes, supplemented by uncertainty analysis, to nuclear safety problems for best estimate (BE) calculations. Four analysis methods are investigated which allow uncertainty statements of varying quality. The CSAU, AEAW, GE and GRS methods are described and their code validation, important parameters, mathematical approach and plant data involved are compared.

Additional information

Authors: FORGE A, CEA, Institut de Protection et de Sûreté Nucléaire, CEN Fontenay-aux-Roses (FR);POCHARD R, CEA, Institut de Protection et de Sûreté Nucléaire, CEN Fontenay-aux-Roses (FR);GLAESER H, ;WOBBHAHN W, ;HOFER E, ;TESCHENDORFF V,
Bibliographic Reference: EUR 15364 EN (1994) 102 pp., FS, ECU 11.50
Availability: (2)
ISBN: ISBN 92-826-3161-3
Record Number: 199410892 / Last updated on: 1994-11-28
Category: PUBLICATION
Original language: en
Available languages: en
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