Modelling of defective CANDU fuel phenomena
Source abstract
Abstract
A mechanistic model is presented for the modelling of defective CANDU fuel behaviour. This physically-based treatment includes a multi-physics coupling of fission product release, fuel oxidation and sheath hydriding phenomena with the occurrence of fuel failure. The stoichiometry deviation profile is used to evaluate effects on the fission-product diffusivity and heat conduction in the fuel. A time-dependent fission product release model accounts for the transport of fission products of the short-lived radioiodine and noble gas isotopes in the fuel matrix with their release into the fuel-to-sheath gap and coolant. Transport of steam and hydrogen gases along the gap is further considered as a boundary condition of the fuel oxidation model. This treatment provides an estimate of the partial pressure ratio of hydrogen-to-steam in the gap for evaluation of the critical ratio necessary for the promotion of sheath hydriding. Secondary hydriding and fuel element deterioration is subsequently evaluated in accordance with a Locke-type correlation.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (62)
Show source-provided references
1. A model for the release of radioactive krypton, xenon, and iodine from defective UO2 fuel elements10.13182/NT86-A16203 ↗
2. Fundamental aspects of defective nuclear fuel behaviour and fission product release10.1016/0022-3115(88)90049-9 ↗
3. Fuel performance and fission product release studies for defected fuel elements10.13182/NT93-A34845 ↗
4. Fission product chemistry in oxide fuels
5. Mechanisms of defection of zircaloy-clad fuel rods by internal hydriding
6. Mechanism of hydrogen absorption by zirconium alloys
7. Internal hydriding in irradiated defected fuel rods
8. Post-Defect Behaviour of Barrier Fuel
9. Framework model for hydrogen redistribution in zircaloy sheathing10.1016/j.jnucmat.2010.12.030 ↗
10. Fission product release from nuclear fuel by recoil and knockout10.1016/0022-3115(87)90515-0 ↗
11. Fission Product release modelling for application of fuel-failure monitoring and detection – An overview10.1016/j.jnucmat.2017.03.037 ↗
12. WANO fuel reliability indicator (FRI) for CANDU fuel
13. A model for fission gas release and fuel oxidation behaviour for defected UO2 fuel Elements10.13182/NT90-A16236 ↗
14. Fuel oxidation and thermal conductivity model for operating defective fuel rods10.1016/S0022-3115(02)01231-X ↗
15. D.R. Olander, W. Wang, Y.S. Kim, C. Li, and K. Lim, “Chemistry of defective light water reactor fuel”, Electric Power Research Institute Report TR-107074, (February 1997).
16. Modeling of fission product release from defective fuel rods under WWER operation conditions and in leakage tests during refueling
17. A conceptual model for the fuel oxidation of defective fuel10.1016/j.jnucmat.2006.12.050 ↗
18. Three-dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in UO2 nuclear fuel rods10.1016/j.jnucmat.2009.03.035 ↗
19. Thermodynamically informed nuclear fuel codes – A review and perspectives10.3390/thermo1020018 ↗
20. Lewis · 2017
21. A Kinetic model for fission-product release and fuel oxidation behaviour for zircaloy-clad fuel elements under reactor accident conditions10.1016/0022-3115(93)90265-Z ↗
22. Chapter 4: fuel-coolant chemical interaction,” in state-of-the-art report on multi-scale modelling of nuclear fuels
23. Reid · 1987
24. Parry · 1980
25. Part II: modeling of fuel oxidation and fission product release behavior for defective fuel
26. A comparison of thermo-oxidation kinetic measurements of Zircaloy-4 in light and heavy water steam
27. Oxygen potential measurements in irradiated mixed oxide fuel
28. Oxygen redistribution in fast reactor oxide fuel10.1016/0022-3115(76)90083-0 ↗
29. The OXIRED model for redistribution of oxygen in non-stoichiometric uranium-plutonium oxides10.1016/0022-3115(87)90088-2 ↗
30. Oxidation of UO2 in air and steam with relevance to fission product releases
31. High temperature oxidation behaviour of UO2 in air and steam
32. Mechanistic interpretations of UO2 oxidation10.1016/S0022-3115(97)00291-2 ↗
33. High temperature oxidation of UO2 in steam-hydrogen mixtures10.1016/0022-3115(94)90201-1 ↗
34. Massih · 2018
35. Modelling oxidation behaviour in operating defective nuclear reactor fuel elements
36. A model for predicting coolant activity behaviour for fuel-failure monitoring analysis10.1016/j.jnucmat.2006.11.015 ↗
37. The chemical state of the fission products in oxide fuels10.1016/0022-3115(85)90460-X ↗
38. Defected zircaloy fuel
39. The behaviour of defective reactor fuel10.1016/0029-5493(72)90080-5 ↗
40. A generalized model for fission-product transport in the fuel-to-sheath gap of defective fuel elements10.1016/0022-3115(90)90210-E ↗
41. Release of short-lived fission products from UO2 fuel: effects of operating conditions10.1016/0022-3115(85)90327-7 ↗
42. Source term of iodine and noble gas fission products in the fuel-to-sheath gap of intact operating nuclear fuel elements10.1016/0022-3115(90)90438-S ↗
43. Measured release of radioactive xenon, krypton and iodine from UO2 during nuclear operation and a comparison with release models
44. Oxygen diffusion in uranium dioxide
45. Mechanisms of fission gas release from defective fuel rods to water coolant during steady-state operation of nuclear power reactors10.1016/j.nucengdes.2018.12.021 ↗
46. Defective PWR fuel rods detection and characterization using an artificial neural network10.1016/j.pnucene.2023.104686 ↗
47. Final report on rod cladding failure during SGTR
48. Simulation of radioactive fission gas release from defective PWR fuel rod using the MFPR/R mechanistic code10.1016/j.jnucmat.2023.154536 ↗
49. Effect of molecular hydrogen on hydrogen peroxide in water radiolysis10.1021/jp012245j ↗
50. A quantitative model of water radiolysis and chemical production rates near radionuclide-containing solids10.1016/j.radphyschem.2015.06.011 ↗
51. An experimental and theoretical treatment of the release of 85Kr from hyperstoichiometric uranium dioxide
52. G. Kagana and J. Rest, “A physical description of fission product behaviour in fuels for advanced power reactors,” Argonne National Laboratory Report, ANL-07/24, September 2007.10.2172/919331 ↗
53. Combined grain-boundary and lattice diffusion in fine-grained ceramics
54. Modelling of iodine induced stress corrosion cracking in Candu fuel10.1016/j.jnucmat.2010.10.063 ↗
55. Escape of fission products from defective fuel rods of light water reactors10.1016/0029-5493(81)90033-9 ↗
56. Release of iodine from defective fuel following reactor shutdown10.13182/NT87-A33970 ↗
57. Post defect deterioration of CANDU fuel: what have we learned
58. Review and update of fuel defect secondary hydriding thresholds
59. Hydrogen embrittlement in hydride forming metals
60. Modelling of the activity of I-129 in the primary coolant of a CANDU reactor10.1016/S0022-3115(02)01588-X ↗
61. The essential CANDU: a textbook on the CANDU nuclear power plant technology
62. J.M. Markowitz, “Internal zirconium hydride formation in zircaloy fuel element cladding under irradiation,” WAPD-TM-351, Bettis Atomic Power Laboratory (May 1963).