Published 2003 | Version v1
Report Open

Hydraulic Characteristics of the Maria Reactor Control Rod Seat

Creators

  • 1. Institute of Atomic Energy, Otwock-Swierk (Poland)

Description

In the work a method and the results of hydraulic measurements accomplished on a mock up of the MARIA reactor control rod are presented. Based on the results received the mathematical equations describing the relations between water velocity in both seat gaps and the pressure drop on beryllium - graphite matrix as well as water temperature were determined. The results enable to perform a more precise thermal - hydraulic analysis of working conditions for the MARIA reactor control rods. (author)

Availability note (English)

Available from INIS in electronic form

Files

35103640.pdf

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Additional details

Additional titles

Original title (Polish)
Charakterystyka hydrauliczna gniazda preta regulacyjnego reaktora Maria

Publishing Information

Imprint Pagination
26 p.
ISSN
1232-5317
Report number
IAE--101/A

INIS

Country of Publication
Poland
Country of Input or Organization
Poland
INIS RN
35103640
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CONTROL ELEMENTS; CONTROL SYSTEMS; HYDRAULICS; MARIA REACTOR; PRIMARY COOLANT CIRCUITS; REACTOR COOLING SYSTEMS; REACTOR CORES; SECONDARY COOLANT CIRCUITS
Descriptors DEC
BERYLLIUM MODERATED REACTORS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICS; METAL MODERATED REACTORS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs., 15 figs., 3 tabs.