Published August 1997 | Version v1
Report Open

Methods for acquiring data in power ramping experiments with WWER fuel rods at high burnup

  • 1. Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation)
  • 2. Institute of Inorganic Materials, Moscow (Russian Federation)

Description

A programme on in-pile test which involve fuel burnup up to 60 MWd/kg and up to 12 fuel rods in the experimental rig is considered. Testing methods with reference to the MIR-M1 reactor are reported. Power ramping regime can be realized either by an increase of the total reactor capacity or by displacement of the nearest to the experimental cell control rods or by combination of these two ways. A total thermal capacity of the fuel rod cluster is determined by means of the thermal balance technique. The thermal capacity of each separate fuel rod can be estimated from the distribution of their relative activity within the accuracy range 5-10%. The important condition for this procedure is to keep the initial distribution of the fuel rod heating during power ramping. Means of instrumentation are described. They are standard detectors of loop facilities and transducers installed both in the irradiation rigs and fuel rods. Different ways of processing data on the fuel rod loss of integrity are reported. When the time of fuel rod loss of tightness is placed in correspondence with its capacity, processing can be made either on the maximum fuel rod heat load or on that at crack location. The information acquired in the experiments on the burnup values, heat rating distribution, kinetics of fission product gas emission, fuel rod elongation, fuel rod diameter changes, crack availability and fission products migration is used for the development and verification of calculation codes. (author). 1 ref., 4 figs, 1 tab

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Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting
Imprint Pagination
559 p.
Journal Page Range
p. 193-200.
ISSN
1011-4289
Report number
IAEA-TECDOC--957

Conference

Title
Technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support.
Dates
19-23 Sep 1994.
Place
Windermere (United Kingdom).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28068460
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; DATA ACQUISITION; FUEL RODS; POWER; REACTOR INSTRUMENTATION; TESTING; VARIATIONS; WWER TYPE REACTORS
Descriptors DEC
ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information