Fuel temperature measurement as an alternative in-core power measuring technique
Creators
- 1. Gesellschaft fuer Kernenergieverwertung in Schiffbau und Schiffahrt m.b.H., Geesthacht-Tesperhude (F.R. Germany)
Description
Fuel temperature measurement is described as an alternative to neutron flux measurement. Thermocouples are incorporated into the fuel rod with minimal disturbance to the lattice. One of the major problems associated with the technique is handling of connector cables along with the fuel element. Fuel temperature measurement has been tested in the Otto Hahn reactor where the first core, FDR-1, was instrumented with 18 sensors in two fuel elements. The second core, FDR-2, had 9 thermocouples installed, of which 3 remained operational at time of reporting. Static measurements were performed at various steady power conditions and output compared to conventional in-core flux detectors. Dynamic fuel temperature measurements also compared favourably with neutron flux measurement. The thermocouple time constant was found to be smaller than that of the fuel pin, giving sufficiently rapid indication of the fuel pin's state. (O.T.)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the IAEA specialists' meeting on in-core instrumentation and failed fuel detection and location, Mississauga, Ontario, Canada, May 13-15, 1974
- Imprint Pagination
- p. 19-39.
- Report number
- AECL--5124
Conference
- Title
- IAEA specialists' meeting on in-core instrumentation and failed fuel detection and location.
- Dates
- 13 May 1974.
- Place
- Mississauga, Ontario, Canada.
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 7244967
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- IN CORE INSTRUMENTS; OTTO HAHN REACTOR; POWER DENSITY; REACTOR INSTRUMENTATION; RELIABILITY; SOLID FUELS; TEMPERATURE MEASUREMENT; TEMPERATURE MONITORING; THERMOCOUPLES
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MEASURING INSTRUMENTS; MONITORING; NUCLEAR FUELS; POWER REACTORS; PROPULSION REACTORS; PWR TYPE REACTORS; REACTOR MATERIALS; REACTORS; SHIP PROPULSION REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS