High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
Name
NFC-058-App.pdf
Description
NFC-058-App
Size
6.41 MB
Format
Adobe PDF
Checksum (MD5)
802e2956940df221f039e8a9a5fb966d
Author(s)
Kazimi, Mujid S.
Hejzlar, Pavel
Ballinger, Ronald G.
Carpenter, David M.
Feng, Dandong
Kohse, Gordon E.
Lee, Won Jae
No, Hee Cheon
Ostrovsky, Yakov
Otsuka, Yasuyuki
Date Issued
August 2003
Publisher
Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program
Series/Report no.
MIT-NFC;
Abstract
B.1.1 VIPRE modeling of PWR core with annular fuel:
Optimization studies in the first year used an isolated channel and models for MDNBR analyses. These analyses provided sufficient knowledge of potential thermal hydraulic performance of annular fuels to select the 13x13 array as the most promising configuration. To obtain more realistic and accurate MDNBR, a whole core model is necessary. In particular, the major concern is correct representation of channel flow rate. The earlier models used the core-average mass flux, which does not account for flow rate reduction in the hot channels due to increased pressure drop in this channel as a result of higher subcooled, or possibly, saturated boiling. Therefore, it is expected that the MDNBR obtained from the full core VIPRE-01 model will be smaller than the values obtained from the isolated channel model.
Description
Progress Report for Work August 2001 through July 2002
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