Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Thermal hydraulic analysis of a tubular fuel assembly in the normal operating condition of Tehran Research Reactor core

Document Type : Research Paper

Authors

M. Hasanzadeh
M. Amin Mozafari
F. Khoshahval
R. Gharari
H. Esmaeili

Nuclear Safety and Reactor Research School, Nuclear Science and Technology Research Institute, AEOI, P.O.Box: 11364-3486, Tehran - Iran

https://doi.org/10.24200/nst.2022.1390
Abstract
The purpose of this paper is to investigate the possibility of using tubular fuel assemblies in Tehran Research Reactor (TRR) from the thermal hydraulic perspective. Tubular fuels have been used successfully in many Russian model research reactors in recent decades. The most important advantages of this fuel are higher neutron flux, more reactivity and less fuel loading compared to the current plate fuels. In this study, by selecting a tubular fuel assembly of IRT-4M type that is more geometrically compatible with the geometry and dimensions of the core grid plate, we modeled it using the Fluent software and also the RELAP5/Mod3.2 code. The thermal hydraulic parameters of this assembly have been calculated under the operating conditions of current MTR fuel. The results of the calculations showed that the maximum clad temperature in both calculation tools is sufficiently lower than 105°C, which indicates that without changing the current flow rate of the core, the heat produced in the tubular fuel can be well removed. Moreover, the maximum fuel temperature in tubular fuel is about 10°C lower than the maximum fuel temperature in the current standard fuel element, which is another advantage for this fuel type.

Highlights

1. V. Rozhikov, et al., Design and Manufacture of Fuel Assemblies for Russian Research Reactors, In Safety Related Issues of Spent Nuclear Fuel Storage, Springer,  95-105 (2007).

 

2. K.A. Konoplev, et al, LEU WWR-M2 fuel qualification, In Proceedings of this Conference, (2002).

 

3. N.A. Hanan, P.L. Garner, Neutronic, steady-state, and transient analyses for the Kazakhstan VVR-K reactor with LEU fuel: ANL independent verification results (No. ANL/RTR/TM-15/7). Argonne National Lab. (ANL), Argonne, IL (United States) (2015).

 

4. AEOI, Safety Analysis Report for Tehran Research Reactor, Chapter 5. (Atomic Energy Organization of Iran, Tehran, Iran, 2009).

 

5. EL Khatib, H.H.A., Thermal-hydraulic simulation and analysis of Research Reactor Cooling Systems.

 

6. B.R. Munson, et al, Fluid mechanics, Singapore: Wiley (2013).

 

7. F.U. Manual, Fluent Inc, Chapter, 6, 14-16 (2003).

 

8. E. Saadati, M. Zainul Abedini, Principles of basic and advanced simulation of computational fluid dynamics using FLUENT and CFX software, First Edition, (1394) (In Persian).

 

9. J.H. Ferziger, M. Peric, Computational methods for fluid dynamics, (1996), Physics Today, 50(3), 80-84 (1981).

 

10. J.J. Chattot, Computational aerodynamics and fluid dynamics: an introduction, Springer Science & Business Media (204).

 

11. D.B. Pelowitz, MCNPX 2.7.0 manual, LANL, LA-CP-07-1473, Los Alamos National Laboratory, (2008).

 

12. M. Hasanzadeh, et al., Neutronic conceptual design of Tehran Research Reactor using tubular fuel, JonSat. (In Press) 10.24200/nst.2020.614.1423 (In Persian).

 

13. D.R. Miller, Critical flow velocities for collapse of reactor parallel-plate fuel assemblies, Journal of Engineering for Power, 82(2), 83-91 (1960).

 

14. R.H. Whittle, R. Forgan, A Correlation for the Minima in the Pressure Drop Versus Flow-Rate Curves for Subcooled Water Flowing in Narrow Heated Channels, Nuclear Engineering and Design, 6, 89-99 (1967).

Keywords

Tubular fuel
Tehran Research Reactor
Thermal hydraulic
Fluent software
RELAP5 code
1. V. Rozhikov, et al., Design and Manufacture of Fuel Assemblies for Russian Research Reactors, In Safety Related Issues of Spent Nuclear Fuel Storage, Springer,  95-105 (2007).
 
2. K.A. Konoplev, et al, LEU WWR-M2 fuel qualification, In Proceedings of this Conference, (2002).
 
3. N.A. Hanan, P.L. Garner, Neutronic, steady-state, and transient analyses for the Kazakhstan VVR-K reactor with LEU fuel: ANL independent verification results (No. ANL/RTR/TM-15/7). Argonne National Lab. (ANL), Argonne, IL (United States) (2015).
 
4. AEOI, Safety Analysis Report for Tehran Research Reactor, Chapter 5. (Atomic Energy Organization of Iran, Tehran, Iran, 2009).
 
5. EL Khatib, H.H.A., Thermal-hydraulic simulation and analysis of Research Reactor Cooling Systems.
 
6. B.R. Munson, et al, Fluid mechanics, Singapore: Wiley (2013).
 
7. F.U. Manual, Fluent Inc, Chapter, 6, 14-16 (2003).
 
8. E. Saadati, M. Zainul Abedini, Principles of basic and advanced simulation of computational fluid dynamics using FLUENT and CFX software, First Edition, (1394) (In Persian).
 
9. J.H. Ferziger, M. Peric, Computational methods for fluid dynamics, (1996), Physics Today, 50(3), 80-84 (1981).
 
10. J.J. Chattot, Computational aerodynamics and fluid dynamics: an introduction, Springer Science & Business Media (204).
 
11. D.B. Pelowitz, MCNPX 2.7.0 manual, LANL, LA-CP-07-1473, Los Alamos National Laboratory, (2008).
 
12. M. Hasanzadeh, et al., Neutronic conceptual design of Tehran Research Reactor using tubular fuel, JonSat. (In Press) 10.24200/nst.2020.614.1423 (In Persian).
 
13. D.R. Miller, Critical flow velocities for collapse of reactor parallel-plate fuel assemblies, Journal of Engineering for Power, 82(2), 83-91 (1960).
 
14. R.H. Whittle, R. Forgan, A Correlation for the Minima in the Pressure Drop Versus Flow-Rate Curves for Subcooled Water Flowing in Narrow Heated Channels, Nuclear Engineering and Design, 6, 89-99 (1967).

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