A simulation of I2S-LWR selected transients
Abstract
The Integral Inherently Safe (I2S-LWR) reactor was designed to improve the safety performance of PWR types reactors, and several design basis accidents were eliminated using innovative approaches to the I2S-LWR plant layout. However, some accidents such as station blackout (SBO), main steam line break (MSLB) type accident – the secondary hot leg break (SHLB) – were deemed statistically relevant, and the work performed here was to simulate these events using the system thermal–hydraulics code RELAP5 coupled to the 3D spatial kinetics code PARCS. The safety response of the reactor to a station blackout is predicted to be acceptable at both beginning of cycle (BOC) and end of cycle EOC core conditions with either the UO2 or U3Si2 fuel options considered here. In the analysis of the SHLB performed here, an unprotected (no SCRAM) condition was assumed to highlight the I2S-LWR capabilities. Results indicate that with the UO2 core, the fuel temperatures rise notably, but no fuel melting was predicted and departure from nucleate boiling ratio (DNBR) limits were not exceeded. Similarly, the U3Si2 fuel performed well, but with lower fuel temperatures and decreased DNBR. Following the break of the steam line in the I2S-LWR, shutdown is achieved after about twomore »
- Authors:
-
- Univ. of Michigan, Ann Arbor, MI (United States). Nuclear Engineering
- Univ. of Michigan, Ann Arbor, MI (United States). Nuclear Engineering; Xian Jiaotong Univ., Xian (China). School of Nuclear Science and Technology
- Brigham Young Univ., Provo, UT (United States). Chemical Engineering
- Publication Date:
- Research Org.:
- Univ. of Michigan, Ann Arbor, MI (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1848138
- Alternate Identifier(s):
- OSTI ID: 1692195
- Grant/Contract Number:
- AC07-05ID14517; NEUP 12-4733
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Annals of Nuclear Energy
- Additional Journal Information:
- Journal Volume: 145; Journal Issue: C; Journal ID: ISSN 0306-4549
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; Nuclear Science & Technology; I2S-LWR; Integral configuration; Inherent safety; Safety analysis
Citation Formats
Ward, Andrew M., Wang, Mingjun, Neumann, Matthew D., Memmott, Matthew, Manera, Annalisa, and Downar, Thomas J. A simulation of I2S-LWR selected transients. United States: N. p., 2017.
Web. doi:10.1016/j.anucene.2017.03.016.
Ward, Andrew M., Wang, Mingjun, Neumann, Matthew D., Memmott, Matthew, Manera, Annalisa, & Downar, Thomas J. A simulation of I2S-LWR selected transients. United States. https://doi.org/10.1016/j.anucene.2017.03.016
Ward, Andrew M., Wang, Mingjun, Neumann, Matthew D., Memmott, Matthew, Manera, Annalisa, and Downar, Thomas J. Fri .
"A simulation of I2S-LWR selected transients". United States. https://doi.org/10.1016/j.anucene.2017.03.016. https://www.osti.gov/servlets/purl/1848138.
@article{osti_1848138,
title = {A simulation of I2S-LWR selected transients},
author = {Ward, Andrew M. and Wang, Mingjun and Neumann, Matthew D. and Memmott, Matthew and Manera, Annalisa and Downar, Thomas J.},
abstractNote = {The Integral Inherently Safe (I2S-LWR) reactor was designed to improve the safety performance of PWR types reactors, and several design basis accidents were eliminated using innovative approaches to the I2S-LWR plant layout. However, some accidents such as station blackout (SBO), main steam line break (MSLB) type accident – the secondary hot leg break (SHLB) – were deemed statistically relevant, and the work performed here was to simulate these events using the system thermal–hydraulics code RELAP5 coupled to the 3D spatial kinetics code PARCS. The safety response of the reactor to a station blackout is predicted to be acceptable at both beginning of cycle (BOC) and end of cycle EOC core conditions with either the UO2 or U3Si2 fuel options considered here. In the analysis of the SHLB performed here, an unprotected (no SCRAM) condition was assumed to highlight the I2S-LWR capabilities. Results indicate that with the UO2 core, the fuel temperatures rise notably, but no fuel melting was predicted and departure from nucleate boiling ratio (DNBR) limits were not exceeded. Similarly, the U3Si2 fuel performed well, but with lower fuel temperatures and decreased DNBR. Following the break of the steam line in the I2S-LWR, shutdown is achieved after about two minutes via negative reactivity from loss of primary flow. In all cases considered, the I2S-LWR appears to accomplish the goals of increased safety performance. Further design improvements and other fuel options may marginally improve on the observed safety performance. Additionally, higher fidelity analysis with the next generation subchannel, Computational Fluid Dynamics (CFD), or full core transport may be useful in refining the prediction of the peak fuel and cladding temperatures, as well limiting DNBR during the accidents.},
doi = {10.1016/j.anucene.2017.03.016},
journal = {Annals of Nuclear Energy},
number = C,
volume = 145,
place = {United States},
year = {Fri Mar 31 00:00:00 EDT 2017},
month = {Fri Mar 31 00:00:00 EDT 2017}
}
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