Determination of Void Fraction Profile in a Boiling Water Reactor Channel Using Neutron Noise Analysis

Autor:	J.E. Mott, W.T. King, D.N. Fry, Atta
Rok vydání:	1978
Předmět:	Materials science Nuclear Energy and Engineering Nuclear reactor core Neutron flux Fission Nuclear engineering Neutron poison Mass flow rate Boiling water reactor Fraction (chemistry) Mechanics Porosity
Zdroj:	Nuclear Science and Engineering. 66:264-268
ISSN:	1943-748X 0029-5639
DOI:	10.13182/nse78-a27209
Popis:	Fluctuations in the neutron flux caused by steam bubbles were analyzed to infer the average void fraction in the four fuel bundles that surround an in-core detector string in a boiling water reactor. The velocity of steam bubbles was inferred from the phase lag between axially displaced in-core fission detectors. This velocity, together with the measured power distribution and mass flow rate, was used to obtain the void fraction as a function of axial position. The results are in agreement with the predictions based on the Zuber et al. model, except near the top of the fuel channel.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::af3a773085e81e138ff1f302005711ae https://doi.org/10.13182/nse78-a27209 Zobrazit plný text záznamu