COMPREHENSIVE ASSESSMENT OF THE ISPRA BWR AND PWR SUBCHANNEL EXPERIMENTS AND CODE ANALYSIS WITH DIFFERENT TWO-PHASE MODELS AND SOLUTION SCHEMES
The first part of this research report describes the facility, the BWR and PWR bundles used, the measurement techniques and their accuracies, and the results of three large test series: for prototypical BWR conditions of 70 bar, for prototypical PWR conditions of 160 bar, and for the PWR bundle under reduced pressure conditions of 70 bar. The second part presents calculational subchannel code results for a cross-section of the subchannel experiments performed. It is conclusively demonstrated that the extra expenditures of using advanced codes such as THERMIT effectively pay off when stringent requirements for optimising LWR fuel rod bundles should be met.
Bibliographic Reference: THIRD INTERNATIONAL TOPICAL MEETING ON REACTOR THERMAL HYDRAULICS, NEWPORT, RHODE ISLAND (USA), OCT. 15- 18, 1985 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32338 ORA
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Record Number: 1989124066600 / Last updated on: 1987-01-01
Available languages: en