Modelling and code development for the improved description of FP and aerosol release during LWR core heat-up and degradation
The final report gives a description of work performed under the 1988-1991 Reactor Safety programme. The main aspects of in-vessel FP behaviour are discussed in view of the aim of the research programme and the model requirements necessary for source term analysis. The present status of the FIPREM code is outlined, including recent changes and improvements made to the physical and chemical models, modules and the overall code structure. Additional results obtained from sensitivity calculations with the integrated KESS-FIPREM code system are given for standard applications, comprising bundle tests and PWR cores. Finally, the progress achieved in the frame of the terminated project is summarised. Further modelling and verification needs are identified.
Bibliographic Reference: EUR 15210 EN (1994) 70 pp., free of charge
Availability: Available from Joint Research Centre, Publication Department, I-21020 Ispra (Va.) (IT)
Record Number: 199511566 / Last updated on: 1995-12-12
Original language: en
Available languages: en