1 |
M. Prasad, R.S. Rao, S.K. Gupta, Assessment methodology for confidence in safety margin for large break loss of coolant accident sequences, Ann. Nucl. Energy 38 (2011) 1225-1230, https://doi.org/10.1016/j.anucene.2011.02.015.
DOI
|
2 |
F. Sanchez-saez, S. Carlos, J.F. Villanueva, A.I. Sanchez, S. Martorell, Uncertainty analysis of PKL SBLOCA G7 . 1 test simulation using TRACE with Wilks and GAM surrogate methods, Nucl. Eng. Des. 319 (2017) 61-72, https://doi.org/10.1016/j.nucengdes.2017.04.037.
DOI
|
3 |
E. Boafo, H.A. Gabbar, Stochastic uncertainty quantification for safety verification applications in nuclear power plants, Ann. Nucl. Energy 113 (2018) 399-408, https://doi.org/10.1016/j.anucene.2017.11.041.
DOI
|
4 |
Y.M. Farawila, Floating filter screen in a lower tie plate box of a nuclear fuel assembly, U.S. Patent Application 10/176,897, filed January 8, 2019.
|
5 |
Y.M. Farawila, Method and Fuel Design to Stabilize Boiling Water Reactors, 14/997, 2017, p. 557, filed July 20.
|
6 |
M.I. Radaideh, Analysis of Reverse Flow Restriction Device to Prevent Fuel Dryout during Loss of Coolant and Instability Accidents of Boiling Water Reactors, Master Thesis, University of Illinois at Urbana Champaign, 2016.
|
7 |
Y.M. Farawila, A method to prevent severe power and flow oscillations in boiling water reactors, in: Proc. 16th Int. Top. Meet. Nucl. React. Therm. Hydraul. NURETH-16, Chicago, Illinois, Aug 30-Sep 4, 2015.
|
8 |
M.I. Radaideh, T. Kozlowski, Y.M. Farawila, Analysis of reverse flow restriction device to prevent fuel dryout damage during boiling water reactor instability, Phys. React. 5 (2016) 3130-3139 (PHYSOR 2016), Sun Valley, Idaho, May 1- 5, 2016.
|
9 |
K. Pettersson, H. Chung, M. Billone, T. Fuketa, F. Nagase, C. Grandjean, Nuclear Fuel Behaviour in Loss-Of-Coolant Accident (LOCA) Conditions, Nuclear Energy Agency, Organisation for Economic Co-Operation and Development., 2009.
|
10 |
S. Bajorek, TRACE V5. 0 Theory Manual, Field Equations, Solution Methods and Physical Models, U.S. Nuclear Regulatory Commission, 2008.
|
11 |
C. Queral, J. Montero-Mayorga, J. Gonzalez-Cadelo, G. Jimenez, AP1000 Large-Break LOCA BEPU analysis with TRACE code, Ann. Nucl. Energy 85 (2015) 576-589, https://doi.org/10.1016/j.anucene.2015.06.011.
DOI
|
12 |
J. Montero-Mayorga, C. Queral, J. Gonzalez-Cadelo, AP1000 SBLOCA simulations with TRACE code, Ann. Nucl. Energy 75 (2015) 87-100, https://doi.org/10.1016/j.anucene.2014.07.045.
DOI
|
13 |
C.-Y. Chen, C. Shih, J.-R. Wang, The alternate mitigation strategies on the extreme event of the LOCA and the SBO with the TRACE Chinshan BWR4 model, Nucl. Eng. Des. 256 (2013) 332-340, https://doi.org/10.1016/j.nucengdes.2012.08.029.
DOI
|
14 |
J. Cho, J.H. Park, D.S. Kim, H.G. Lim, Quantification of LOCA core damage frequency based on thermal-hydraulics analysis, Nucl. Eng. Des. 315 (2017) 77-92, https://doi.org/10.1016/j.nucengdes.2017.02.023.
DOI
|
15 |
T. Mui, T. Kozlowski, Confirmation of Wilks' method applied to TRACE model of boiling water reactor spray cooling experiment, Ann. Nucl. Energy 117 (2018) 53-59, https://doi.org/10.1016/j.anucene.2018.03.011.
DOI
|