Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon |
Jha, Alok
(Homi Bhabha National Institute)
Gupta, Anurag (HBNI) Das, Rajarshi (Station Reactor Physicist, Kakrapar Atomic Power Project NPCIL) Paraswar, Shantanu D. (Tarapur Atomic Power Station - 3&4, NPCIL) |
1 | International Atomic Energy Agency, In-core Fuel Management Programs for Nuclear Power Reactors (Final Report of the Co-ordinated Research Programme), INTERNATIONAL ATOMIC ENERGY AGENCY, Vienna, 1984. IAEA-TECDOC-314. |
2 | D. Lanning, C. Hann, Review of Methods Applicable to the Calculation of Gap Conductance in Zircaloy-Clad Uo 2 Fuel Rods, Technical report, Battelle Pacific Northwest Labs, 1975. |
3 | A.L. Loeb, Thermal conductivity: Viii, a theory of thermal conductivity of porous materials, J. Am. Ceram. Soc. 37 (2) (1954) 96-99. |
4 | F. Nichols, H. Warner, Swelling and Gas-Release Models for Oxide Fuel Rods (Lwbr Development Program), Technical report, Westinghouse Electric Corp., West Mifflin, Pa, 1971. |
5 | G. Reymann, Matproeversion 10: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior. Technical report, Idaho National Engineering Lab, 1978. |
6 | A. Ross, The Dependence of the Thermal Conductivity of Uranium Dioxide on Density, Microstructure, Stoichiometry and Thermal-Neutron Irradiation, Technical report, Atomic Energy of Canada Ltd., Chalk River,, 1960. Ontario (Canada). |
7 | S.K. Gupta, B.K. Dutta, V. Venkat Raj, A. Kokodkar, et al., A study of the Indian PHWR reactor channel under prolonged deteriorated flow conditions, nternational Atomic Energy Agency (IAEA) 984 (1997). |
8 | M. Das, B.V. Arunakumar, P.N. Prasad, Modification in the FUDA computer code to predict fuel performance at high burnup, International Atomic Energy Agency (IAEA) 957 (1997). |
9 | F. Dittus, L. Boelter 2, University of california publications on engineering, 1930, p. 371. |
10 | A.P. Colburn, A method of correlating forced convection heat-transfer data and a comparison with fluid friction, Int. J. Heat Mass Tran. 7 (12) (1964) 1359-1384. |
11 | A. Feith, Thermal Conductivity of Several Ceramic Materials to 2500 Deg C, Technical report, General Electric Co., Cincinnati, Ohio, 1964 (Nuclear Materials and Propulsion Operation). |
12 | J. Rest, Grass-sst: a comprehensive, mechanistic model for the prediction of fission-gas behavior in uo/sub 2/-base fuels during steady-state and transient conditions, Technical report, Argonne National Lab., IL (USA), 1978. |
13 | K. Lassmann, F. Pazdera, Urgap: a gap conductance model for transient conditions, 1983 (Technical report). |
14 | A. Ross, R. Stoute, Heat Transfer Coefficient between Uo 2 and Zircaloy-2, Technical report, Atomic Energy of Canada Limited, 1962. |
15 | K. Srinivasan, H. Purandare, Triveni, 3-d Fuel Management for Phwr Candu, 1985. |
16 | N.E. Todreas, M.S. Kazimi, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, CRC press, 2011. |
17 | R.M. Tripathi, R. Soni, P. Prasad, P. Pandarinathan, Modeling of phwr fuel elements using fuda code. Theme Meeting on Recent Advances in Postirradiation Examination: Programme and Abstracts, 2008. |
18 | H. Warner, F. Nichols, A statistical fuel swelling and fission gas release model, Nucl. Appl. Technol. 9 (2) (1970) 148-166. |
19 | W. Wisenack, Fuel Temperature Modelling and Phenomena: Pellet-Clad Gap Heat Transfer, Fuel Temperature Distribution, OECD Halden Reactor Project, 2010. Technical report. |
20 | J. Christensen, A. Bush, H. Ferrari, R. Allio, Uranium dioxide thermal conductivity, Trans. Am. Nucl. Soc. 7 (1964). |
21 | C.-Y. Li, S. Pati, R. Poeppel, R. Scattergood, R. Weeks, Some considerations of the behavior of fission gas bubbles in mixed-oxide fuels, Nucl. Appl. Technol. 9 (2) (1970) 188-194. |
22 | M. Notley, A computer program to predict the performance of uo2 fuel elements irradiated at high power outputs to a burnup of 10 000 mwd/mtu, Nucl. Appl. Technol. 9 (2) (1970) 195-204. |
23 | J. Robertson, A. Ross, M. Notley, J. MacEwan, Temperature distribution in uo2 fuel elements, J. Nucl. Mater. 7 (3) (1962) 225-262. |
24 | M. Saksena, S. Saxena, Thermal conductivity of mixtures of monatomic gases, Proc. Natl. Inst. Sci. India: Phys. Sci. 31 (1963) 26. |
25 | J. Ainscough, Gap Conductance in Zircaloy-Clad Lwr Fuel Rods, Organisation for Economic Co-Operation and Development-Nuclear Energy Agency, 1982. Technical report. |
26 | H. Das, S.A. Bhardwaj, Fuel Design Analysis Code - FUDA, PPED internal report, IAEA TecDoc 998 (1981) 172-243. |
27 | L. Tong, J. Weisman, Thermal Analysis of Pressurized Water Reactors, ANS, 2016. |
28 | M. Wood, J. Matthews, A simple operational gas release and swelling model: I. intragranular gas, J. Nucl. Mater. 91 (1) (1980) 35-40. |
29 | International Atomic Energy Agency, In-core Fuel Management Programs for Nuclear Power Reactors, INTERNATIONAL ATOMIC ENERGY AGENCY, Vienna, 1996. IAEA-TECDOC-887. |
30 | H. Warner, Bubl-1: a Statistical Fuel Swelling and Fission Gas Release Model (Lwbr Development Program), Technical report, Bettis Atomic Power Lab., Pittsburgh,, 1970. PA (USA). |