Published May 2017 | Version v1
Miscellaneous

Effect of Correlation Uncertainty Distribution on Design Limit CHFR

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

The design limit CHFR is evaluated deterministically with the correlation uncertainty alone, and the actual CHFR of the fuel is estimated conservatively determined with a hot channel factor (HCF) to consider the uncertainty of the heat flux from the fuel. This approach gives clear insight about the probabilistic information, and also decreases unnecessary conservatism of estimation. The statistical determination of design limit CHFR depends primarily on the distribution of correlation uncertainty, which is assumed on the actual experimental data. Since the experimental data does not coincide with the ideal distribution of normal or uniform, the proper assumption on the distribution is critical for the statistical determination of design limit CHFR. In this paper, the effect of the correlation distribution assumption on a design limit CHFR is examined for two different CHF correlations, Mirshak and Kaminaga. The design limit CHFR is estimated for different CHF correlations and different assumptions on the uncertainty distributions. Mirshak and Kaminaga correlation are selected as the CHF correlation and the design limit CHFR are estimated for them. The uncertainty distribution on Mirshak correlation is more similar to uniform than normal, therefore the uniform assumption on the distributions gives proper estimation on design limit CHFR with the correlation. The uncertainty of the correlation need to be defined for predicted/measured since the formulation of random normalized CHFR has the correlation uncertainty factor at the numerator. Defining the uncertainty for predicted/measured, the uncertainty distribution of Kaminaga correlation can be assumed as a normal distribution, and the design limit CHFR is less conservatively estimated comparing to that defined for measured/predicted.

Part of:
Proceedings of the KNS 2017 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Spring Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2017 Spring Meeting of the KNS
Dates
17-19 May 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49050253
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
CORRELATIONS; CRITICAL HEAT FLUX; DESIGN; EXPERIMENTAL DATA; FORECASTING
Descriptors DEC
DATA; HEAT FLUX; INFORMATION; NUMERICAL DATA

Optional Information

Notes
6 refs, 4 figs, 2 tabs