1 |
MATPRO - Version 11, A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior. NUREG/CR-0497 TREE-1280, February 1979.
|
2 |
K.M. Becker, J. Engstrom, O. Nylund, B. Scholin, B. Soderquist, Analysis of the dryout incident in the oskarshamn 2 boiling water reactor, Int. J. Multiph. Flow 16 (6) (1990) 959-974. November-December.
DOI
|
3 |
Ines Gunther-Leopold, Marlene Krois, Judith Kobler Waldis, Hanspeter Linder, Sousan Abolhassani, Investigation of fuel crud by means of ICP-MS and TEM, Procedia Chem. 7 (2012) 673-678.
DOI
|
4 |
N. Cinosi, I. Haq, M. Bluck, S.P. Walker, The effective thermal conductivity of crud and heat transfer from crud-coated PWR fuel, Nucl. Eng. Des. 241 (2011) 792-798.
DOI
|
5 |
Mats Ullberg, Gunnar Lysell, Ann-Charlotte Nystrand, Shadow corrosion mechanisms of zircaloy. SKI Report 28, 2004. February 2004.
|
6 |
A. Medvedev, Y. Bibilashvili, S. Bogatyr, G. Khvostov, Modelling of WWER-1000 fuel: state and prospects, in: Proc.: Conference on VVER Reactor Fuel Performance, Modelling and Experimental Support. St. Constantine, Varna, Bulgaria, November 1994.
|
7 |
A. Medvedev, S. Bogatyr, V. Kouznetsov, G. Khvostov, V. Lagovsky, L. Korystin, V. Poudov, Fuel rod behavior at high burnup WWER fuel cycles, in: Proc.: 5th International Conference on WWER Fuel Performance, Modeling and Experimental Support, Congress Center Albena, Bulgaria, 2003, 29 September - 3 October.
|
8 |
Nuclear Fuel Safety Criteria Technical Review, second ed., OECD/NEA Report, 2012, ISBN 978-92-64-99178-1. OECD-NEA web: https://www.oecd-nea.org/nsd/reports/2012/nea7072-fuel-safety-criteria.pdf.
|
9 |
Improvement of Computer Codes Used for Fuel Behaviour Simulation (FUMEX-III) - Report of a Coordinated Research Project 2008-2012. IAEA Report, IAEA-TECDOC-1697.
|
10 |
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, W. Wiesenack, Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high-burnup KKL BWR fuels, Nucl. Eng. Des. 305 (2016) 559-568.
DOI
|
11 |
EPRI Product Id 1011307, Fuel analysis and licensing Code: FALCON MOD01: volume 1: theoretical and numerical bases, EPRI web: https://www.epri.com/#/pages/product/000000000001011307/, 2004.
|
12 |
EPRI Product Id 1011309, Fuel analysis and licensing code: FALCON MOD01: volume 3: verification and validation, EPRI web, https://www.epri.com/#/pages/product/000000000001011309/, 2004.
|
13 |
G. Khvostov, Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring, Nucl. Eng. Technol. 50 (2018) 1190-1197.
DOI
|
14 |
Technical and Regulatory Basis, Acceptance criteria and guidance for the reactivity-initiated accident, USNRC Memorand. 16 (2015).
|
15 |
G. Khvostov, W. Wiesenack, Analysis of selected Halden overpressure tests using the FALCON code nuclear engineering and design, Nucl. Eng. Des. 310 (2016) 395-409.
DOI
|
16 |
US Nuclear regulatory Commission standard Review plan 4.2 e fuel system design, (USNRC SRP 4.2), NUREG-0800 Rev 3, March 2007.
|
17 |
M. Bales, Establishing analytical limits for zirconium-alloy cladding Material. U.S. NRC Regulatory Guide 1.224 - Preliminary Draft DG-1263, March 2014. US-NRC web: https://www.nrc.gov/docs/ML1528/ML15281A192.pdf. (Accessed 11 July 2019).
|
18 |
G. Khvostov, K. Mikityuk, M.A. Zimmermann, A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code, Nucl. Eng. Des. 241 (2011) 2983-3007.
DOI
|
19 |
G. Khvostov, A dynamic model for fission gas release and gaseous swelling integrated into the FALCON fuel analysis and licensing code, in: Proceedings of the conference: Top Fuel, Paris, France, September 6-10, 2009, 2009. Paper 2085.
|
20 |
G. Khvostov, Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA, Nucl. Eng. Des. 328 (2018) 36-57.
DOI
|
21 |
F. Ribeiro, G. Khvostov, Multi-scale approach to advanced fuel modelling for enhanced safety, Prog. Nucl. Energy 84 (2015) 24-35.
DOI
|
22 |
M. Limback, T. Andersson, A model for analysis of the effects of final annealing on the in- and out-of-reactor creep behaviour of zircaloy cladding, in: E.R. Bradley, G.P. Sabol (Eds.), ASTM STP 1295, American Society for Testing and Materials, 1996, pp. 448-468.
|
23 |
P. Blanpain, X. Thibault, J.-P. Pages, Recent results from the in-reactor MOX fuel performance in France and improvement program, in: Proc.: International Topical Meeting on Light Water Reactor Fuel Performance, Portland Oregon, 1997. March 2-6.
|
24 |
K.V. Moore, et al., RETRAN - A Program for One-Dimensional Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems, vol. 1, EPRI CCM-5, December, 1978.
|
25 |
C.W. Stewart, VIPRE-01: A Thermal-Hydraulic Code for Reactor Cores vol. 1, July 1985. Mathematical Modeling (Revision 2). NP-2511-CCM.
|
26 |
EPRI Product Id 1011308, Fuel Analysis and Licensing Code: FALCON MOD01: Volume 2: User's Manual. EPRI Web. https://www.epri.com/#/pages/product/000000000001011308/, 2004.
|
27 |
A.T. Motta, A. Couet, R.J. Comstock, Corrosion of zirconium alloys used for nuclear fuel cladding, Annu. Rev. Mater. Res. 45 (2015) 311-343.
DOI
|
28 |
G. Khvostov, V. Novikov, A. Medvedev, S. Bogatyr, Approaches to modeling of high burn-up structure and analysis of its effects on the behaviour of light water reactor fuels in the START-3 fuel performance code, in: Proc.: 2005 LWR Fuel Performance Meeting, Kyoto, Japan, October 2005.
|
29 |
G. Ledergerber, S. Valizadeh, J. Wright, M. Limback, L. Hallstadius, D. Gavillet, S. Abolhassani, F. Nagase, T. Sugiyama, W. Wiesenack, T. Tverberg, Fuel behaviour beyond design - exploring the limits, in: Proceedings of the conference: 2010 LWR Fuel Performance/TopFuel/WRFPM, Orlando, Florida, USA, September 26-29, 2010, 2008. Paper 0044.
|
30 |
G. Khvostov, W. Lyon, M. Zimmermann, Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface, Ann. Nucl. Energy 62 (2013) 398-412.
DOI
|
31 |
Review of Fuel Failures in Water Cooled Reactors, IAEA Nuclear Energy Series, 2010. No. NF-T-2.1.
|