Published July 2022 | Version v1
Report

Application of an Improved Technique for Burnup Evaluation of WWER Leaking Fuel Based on the Data on Spiking Events

  • 1. SRC RF TRINITI, Troitsk (Russian Federation)
  • 2. NRC Kurchatov Institute, P.N. Lebedev Physical Institute, RAS, Moscow (Russian Federation)

Description

A conventional approach to evaluating burnup of the leaking fuel assemblies (LFA) at operating WWER power units is to use a burnup correlation of 134Cs/137Cs activity ratio in the primary coolant during spiking events. This technique was revised in an updated regulatory document, considering the differences in evolution of cesium (Cs) content in fuel pellets and in voids inside a fuel rod. However, from 2000s , analysis of spiking events and data of post-irradiation examinations (PIEs) show this technique to be rather inaccurate in some cases. Recent NPP data on activity spiking events at WWER-1000 power units and LFAs examination results have filled the data gap in the burnup range of 40-50 MWd/kgU for Cs inventory in fuel rods with initial enrichment of 4.95 wt%. This new data enables a thorough comparative analysis of systematic factors causing deviation of experimental estimates compared to the results of the conventional technique for various fuel enrichments including fuel with solid fuel pellets. The paper briefly describes an improved technique introduced previously for express calculation of build-up of Cs isotopes in fuel pellets for every fuel rod in the core. This approach employs the NPPs results of routine neutronic calculations of actual pin-wise linear heat generation rate (LHGR) for each fuel cycle with a particular core loading pattern. The activity ratios A(134Cs)/A(137Cs) in fuel calculated in the frame of this technique show good agreement with the available NPP data for LFAs with solid fuel pellets and are also compared to the new RIAR PIE data. It is suggested that an increased reliability in evaluation of leaking fuel burnup at operating WWERs and subsequent LFAs identification could be achieved if the key factors affecting evolution of 134Cs/137Cs activity ratio for each FA in the core are considered simultaneously with distinctive features of mass transfer in leaking fuel rods of different design. (author)

Part of:
Fuel Failure in Normal Operation of Water Reactors: Experience, Causes and Mitigation. Proceedings of a Technical Meeting

Additional details

Publishing Information

ISBN
978-92-0-126022-2
Imprint Title
Fuel Failure in Normal Operation of Water Reactors: Experience, Causes and Mitigation. Proceedings of a Technical Meeting
Imprint Pagination
268 p.
Journal Page Range
p. 83-95
ISSN
1011-4289
Report number
IAEA-TECDOC--2004

Conference

Title
Experience, Causes and Mitigation
Acronym
Technical Meeting on Fuel Failure in Normal Operation of Water Reactors
Dates
14-18 Dec 2020
Place
Vienna (Austria)

Optional Information

Notes
22 refs., 8 figs., 1 tab.