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author 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
Stahl, Peter
Xu, Zhiwen
Yuan, Yi
Zhang, Jiyun
Feinroth, Herbert
Hao, Bernard
Lahoda, Edward J.
Mazzoccoli, Jason P.
Sundaram, Ramu K.
Hamilton, Holly
author2 Massachusetts Institute of Technology. Nuclear Fuel Cycle Program
author_facet Massachusetts Institute of Technology. Nuclear Fuel Cycle Program
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
Stahl, Peter
Xu, Zhiwen
Yuan, Yi
Zhang, Jiyun
Feinroth, Herbert
Hao, Bernard
Lahoda, Edward J.
Mazzoccoli, Jason P.
Sundaram, Ramu K.
Hamilton, Holly
author_sort Kazimi, Mujid S.
collection MIT
description Progress Report for Work August 2001 through July 2002
first_indexed 2024-09-23T15:43:02Z
format Technical Report
id mit-1721.1/75735
institution Massachusetts Institute of Technology
last_indexed 2024-09-23T15:43:02Z
publishDate 2012
publisher Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program
record_format dspace
spelling mit-1721.1/757352019-04-11T02:55:10Z High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report 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 Stahl, Peter Xu, Zhiwen Yuan, Yi Zhang, Jiyun Feinroth, Herbert Hao, Bernard Lahoda, Edward J. Mazzoccoli, Jason P. Sundaram, Ramu K. Hamilton, Holly Massachusetts Institute of Technology. Nuclear Fuel Cycle Program 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 Stahl, Peter Xu, Zhiwen Yuan, Yi Zhang, Jiyun Progress Report for Work August 2001 through July 2002 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. 2012-12-17T16:47:26Z 2012-12-17T16:47:26Z 2003-08 Technical Report http://hdl.handle.net/1721.1/75735 MIT-NFC; application/pdf Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program
spellingShingle 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
Stahl, Peter
Xu, Zhiwen
Yuan, Yi
Zhang, Jiyun
Feinroth, Herbert
Hao, Bernard
Lahoda, Edward J.
Mazzoccoli, Jason P.
Sundaram, Ramu K.
Hamilton, Holly
High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
title High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
title_full High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
title_fullStr High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
title_full_unstemmed High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
title_short High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
title_sort high performance fuel design for next generation pwrs appendices b i to fy 02 annual report
url http://hdl.handle.net/1721.1/75735
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