You need JavaScript to view this

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

Abstract

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  More>>
Authors:
Bobrov, S N; Grachev, A F; Ovchinnikov, V A; Poliakov, I S; Matveev, N P; [1]  Novikov, V V [2] 
  1. Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation)
  2. Institute of Inorganic Materials, Moscow (Russian Federation)
Publication Date:
Aug 01, 1997
Product Type:
Conference
Report Number:
IAEA-TECDOC-957; CONF-9409411-
Reference Number:
SCA: 210200; PA: AIX-28:068460; EDB-97:129950; SN: 97001863066
Resource Relation:
Conference: IAEA technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support, Windermere (United Kingdom), 19-23 Sep 1994; Other Information: PBD: Aug 1997; Related Information: Is Part Of Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting; PB: 559 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FUEL RODS; DATA ACQUISITION; BURNUP; POWER; REACTOR INSTRUMENTATION; TESTING; VARIATIONS; WWER TYPE REACTORS
OSTI ID:
534356
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE98602336; TRN: XA9744799068460
Availability:
INIS; OSTI as DE98602336
Submitting Site:
INIS
Size:
pp. 193-200
Announcement Date:

Citation Formats

Bobrov, S N, Grachev, A F, Ovchinnikov, V A, Poliakov, I S, Matveev, N P, and Novikov, V V. Methods for acquiring data in power ramping experiments with WWER fuel rods at high burnup. IAEA: N. p., 1997. Web.
Bobrov, S N, Grachev, A F, Ovchinnikov, V A, Poliakov, I S, Matveev, N P, & Novikov, V V. Methods for acquiring data in power ramping experiments with WWER fuel rods at high burnup. IAEA.
Bobrov, S N, Grachev, A F, Ovchinnikov, V A, Poliakov, I S, Matveev, N P, and Novikov, V V. 1997. "Methods for acquiring data in power ramping experiments with WWER fuel rods at high burnup." IAEA.
@misc{etde_534356,
title = {Methods for acquiring data in power ramping experiments with WWER fuel rods at high burnup}
author = {Bobrov, S N, Grachev, A F, Ovchinnikov, V A, Poliakov, I S, Matveev, N P, and Novikov, V V}
abstractNote = {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.}
place = {IAEA}
year = {1997}
month = {Aug}
}