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Content archived on 2022-12-05

Revaporisation of tests on samples from phebus fission products

Objective



1. OBJECTIVES
In the late phase of a severe water reactor accident, fission products deposited earlier on primary circuit surfaces may experience increasing temperatures by heal transfer from the surrounding gas or radiating corium or by their own decay heat.
For some accident scenarios, a large fraction of the volatile species is predicted to deposit in the reactor coolant system early in the sequence. This fraction has the potential for release later in the sequence, perhaps at a time when the containment has failed and offers little attenuation to the source term. The extent to which the deposition results in permanent retention / removal from consideration is, therefore, a key issue. Safety assessments have highlighted the potential importance of revaporisation and addressing the uncertainties associated with revaporisation phenomena is now an internationally-recognised priority.
The Phebus-FP experiments provide a unique opportunity to acquire realistic irradiated samples with which to study revaporisation by detailed analyses of samples generated from the Phebus FP programme together with supporting separate - effects studies and model developments.
The project objective is to investigate the importance of revaporisation for the reactor source term, with the following experimental programme: A)
- recover circuit portions from a number of l'hebus Fl' tests - characterise the initial state of the deposits
- revaporise the deposits - measure the kinetics of the revaporisation - characterise the secondary deposits and the final state
of the original deposits and hence characterise the physics and chemistry of the re-emission
B) This will be supported by:
- separate-effects tests to quantify the revaporisation phenomena and provide data from simple cases (both inactive and active simulated samples) to interpret the releases from the more complex l'hebus FP samples. - development of models, as well as pre-test calculations, which will, together with the separate effects data, facilitate interpretation and quantification as well as the transposition of data to the reactor case. With this additional information the timing and nature of the reactor source tern- release in an accident can be assessed.

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Coordinator

United Kingdom Atomic Energy Authority (UKAEA)
EU contribution
No data
Address
Winfrith Technology Centre
DT2 8DH Dorchester
United Kingdom

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Total cost

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Participants (2)

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