In cooperation with the Iranian Nuclear Society

Neutronic conceptual design of Tehran Research Reactor using tubular fuel

Document Type : Research Paper

Authors

Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, P.O.Box: 14155-1339, Tehran - Iran

Abstract
The purpose of this paper is to investigate the possibility of using fuel with annular geometry (Tubular) in Tehran research reactor (TRR) from a neutronic perspective. The use of annular fuels requires less fuel load due to higher flux generation and higher reactivity. It is noteworthy that one of the most important advantages of this type of fuel is the creation of an area in the center of the fuel complex for irradiation of materials and production of radiopharmaceuticals. Therefore, in the TRR, a new fuel with annular geometry has been adopted to replace the current fuel with cubic geometry. This fuel is similar to TRR fuel in terms of materials. For this purpose, the neutron conditions of the core are simulated using MCNPX2.7 and WIMS-CITATION codes. Then the obtained results from these codes were compared with the SAR results of the TRR. The obtained results in this paper show that to achieve the reactivity equivalent to the first core of the TRR, the critical mass of the tubular core fuel is up to 17% less than the critical mass of the first core fuel. On the other hand, using annular fuel, the neutron flux in the radiation channels increases up to about 14%. Also, according to the results of this study, the proposed tubular core, a core with an arrangement of 16 and at least 8 packages of 6 control rods are needed to achieve safety standards.

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

 

4. CITATION-LDI, Nuclear Reactor Core Analysis Code System Contributed by: Oak Ridge National Laboratory Oak Ridge, Tennessee "CCC-643 CITATION-LDI 2".

 

5. N.A. Hanan, et al, Feasibility studies for LEU conversion of the WWR-SM reactor in Uzbekistan using pin-type and tubular fuels, No. INIS-XA-C--007. (2003).

 

6. P.L. Garner, N.A. Hanan, Neutronics, steady-state, and transient analyses for the Poland MARIA reactor for irradiation testing of LEU lead test fuel assemblies from CERCA: ANL independent verification results, No. ANL/08/27. Argonne National Lab (ANL), Argonne, IL (United States), (2011).

 

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

 

8. H. Khaleghi, M. Hasanzadeh, Analysis of the thermal feedback and burn up effects on kinetic parameters in TRR by the Monte Carlo method, Journal of Physics Communications, 3, (2018).

Keywords


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. D.B. Pelowitz, MCNPX 2.7.0 manual, LANL, LA-CP-07-1473. Los Alamos National Laboratory, (2008).
 
4. CITATION-LDI, Nuclear Reactor Core Analysis Code System Contributed by: Oak Ridge National Laboratory Oak Ridge, Tennessee "CCC-643 CITATION-LDI 2".
 
5. N.A. Hanan, et al, Feasibility studies for LEU conversion of the WWR-SM reactor in Uzbekistan using pin-type and tubular fuels, No. INIS-XA-C--007. (2003).
 
6. P.L. Garner, N.A. Hanan, Neutronics, steady-state, and transient analyses for the Poland MARIA reactor for irradiation testing of LEU lead test fuel assemblies from CERCA: ANL independent verification results, No. ANL/08/27. Argonne National Lab (ANL), Argonne, IL (United States), (2011).
 
7. AEOI, Safety Analysis Report for Tehran Research Reactor, (Atomic Energy Organization of Iran, Tehran, Iran, 2009).
 
8. H. Khaleghi, M. Hasanzadeh, Analysis of the thermal feedback and burn up effects on kinetic parameters in TRR by the Monte Carlo method, Journal of Physics Communications, 3, (2018).