Published October 2010 | Version v1
Miscellaneous Metadata-only

Study on Calculation of Uncertainty and Range of Ageing Elements using Measured Data of Fuel Channel Flow Rate

Creators

  • 1. Seoul National University, Seoul (Korea, Republic of)

Description

As a part of development the evaluation system of safety margin effects for degradation of CANDU reactors, it is required the selection of ageing elements to analyze the thermal-hydraulic effects using RELAP-CANDU code. Unfortunately, it is not easy to make an explicit relation between the RELAP-CANDU parameters and ageing mechanism because of insufficient data and lack of applicable models. So, in this study, to compensate lack of data and applicable models, measured data of fuel channel flow rate related with ageing are used for determination of range and uncertainty of ageing elements. Then, degradation model is upgraded through application of this result

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2010 autumn meeting of the KNS
Dates
21-22 Oct 2010
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42085187
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AGING; COMPUTER CALCULATIONS; FLOW RATE; FUEL CHANNELS; SAFETY MARGINS
Descriptors DEC
REACTOR CHANNELS; REACTOR COMPONENTS

Optional Information

Notes
6 refs, 2 figs, 3 tabs