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

Simulation of Pulsed Neutron Source Experiment in Tehran Research Reactor Core (TRR)

Document Type : Scientific Note

Author

M. Arkani

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

https://doi.org/10.24200/nst.2022.1362
Abstract
One of the useful methods for measuring fast neutron decay constant in a nuclear reactor core is the pulsed neutron source experiment as MCNP code is based on the Monte Carlo method, so able to track the time-dependent behavior of the particles in static systems. In this research, this capability is utilized, and a pulsed neutron source experiment in the Tehran research reactor (TRR) core is simulated. For this purpose, the system of TRR core at different subcritical states is investigated, and fast neutron decay constant is estimated at each state. Therefore, kinetic parameters of the reactor core are also calculated utilizing the fast neutron decay constant of the core. Calculated values agree with the other results reported in the literature.

Highlights

1. D.L. Hetrick, Dynamics of Nuclear Reactors, The University of Chicago Press (1971).

 

2. G.R. Keepin, Physics of nuclear kinetics, Addison-Wesley Pub. Co (1965).

 

3. B. Verboomen, W. Haeck, P. Baeten, Monte Carlo calculation of the effective neutron generation time. Ann. Nucl. Energy, 33, 911–916 (2006).

 

4. S.A.H. Feghhi, M. Shahriari, H. Afarideh, Calculation of Neutron Importance Function in Fissionable Assemblies Using Monte Carlo Method, Annals of Nuclear Energy, 34, 514-520 (2007).

 

5. M. Arkani, et al., Calculation of six-group importance weighted delayed neutron fractions and prompt neutron lifetime of MTR research reactors based on Monte Carlo method, Progress in Nuclear Energy, 88, 352-363 (2016).

 

6. M.M. Bretscher, Evaluation of reactor kinetic parameters without the need for perturbation codes, Argonne National Laboratory, Argonne, Illinois USA (1997).

 

7. L. Snoj, et al., Monte Carlo calculation of kinetic parameters for the TRIGA Mark II Research Reactor, Nuclear Energy for New Europe (2008).

 

8. L.N. Ussachoff, Equation for the Importance of Neutrons, Reactor Kinetics and the Theory of Perturbation, In: Proc. 1st Intern. Conf. Peaceful Uses Atomic Energy, Geneva, Switzerland, 5, 503 (1955).

 

9. M. Arkani, et al., Prompt Neutron Decay Constant in Esfahan Light Water Subcritical Reactor (ELWSCR): Comparison of Rossi-α Experiment and Monte Carlo Simulation, Iranian Journal of Nuclear Science and Technology, 80, 18-24 (2017) (Published in Persian).

 

10. M. Arkani, et al., Measurement of prompt neutron decay constant of Esfahan light water subcritical reactor utilizing Feynman-α method, Iranian Journal of Nuclear Science and Technology, 76, 1-7 (2016) (Published in Persian).

 

11. K. Beckurts, Measurements with a Pulsed Neutron Source, Nuclear Science and Engineering, 2(4), 516 (1957).

 

12. E. Garelis, J.L. Russell Jr, Theory of pulsed neutron source measurements, Nuclear Science and Engineering, 16, 263 (1963).

 

13. D.B. Pelowitz, MCNPXTM 2.6.0, User´s Manual, Version 2.6.0, Los Alamos National Laboratory, LA-CP-07-1473 (2008).

 

14. Mathworks, MATLAB Reference Guide. The Mathworks Inc (2018).

 

15. A.F. Henry, Nuclear-Reactor Analysis, The MIT Press (1975).

 

16. T.B. Fowler, D.R. Vondy, G.W. Cunninghan, Nuclear reactor core analysis code-citation, USAEC, Report ORNL-TM-2496, ORNL-4078, ReV.2 (1971).

 

17. M. Zaker, Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor, Annals of Nuclear Energy, 30, Issue 15, 1591-1596, (2003).

 

18. S.C. Bailoche, MTR_PC Nuclear Engineering Division, INVAP, Argentina (2001).

 

19. C.M. Persson, et al., Pulsed neutron source measurements in the subcritical ADS experiment YALINA-Booster, Annals of Nuclear Energy, 35, 2357–2364 (2008).

 

20. TRR Safety Analysis Report, Safety Analysis Report for Tehran Research Reactor, Atomic Energy Organization of Iran (2011).

Keywords

Prompt neutron decay constant
Pulsed neutron source experiment
MCNPX code
Reactor core kinetic parameter
1. D.L. Hetrick, Dynamics of Nuclear Reactors, The University of Chicago Press (1971).
 
2. G.R. Keepin, Physics of nuclear kinetics, Addison-Wesley Pub. Co (1965).
 
3. B. Verboomen, W. Haeck, P. Baeten, Monte Carlo calculation of the effective neutron generation time. Ann. Nucl. Energy, 33, 911–916 (2006).
 
4. S.A.H. Feghhi, M. Shahriari, H. Afarideh, Calculation of Neutron Importance Function in Fissionable Assemblies Using Monte Carlo Method, Annals of Nuclear Energy, 34, 514-520 (2007).
 
5. M. Arkani, et al., Calculation of six-group importance weighted delayed neutron fractions and prompt neutron lifetime of MTR research reactors based on Monte Carlo method, Progress in Nuclear Energy, 88, 352-363 (2016).
 
6. M.M. Bretscher, Evaluation of reactor kinetic parameters without the need for perturbation codes, Argonne National Laboratory, Argonne, Illinois USA (1997).
 
7. L. Snoj, et al., Monte Carlo calculation of kinetic parameters for the TRIGA Mark II Research Reactor, Nuclear Energy for New Europe (2008).
 
8. L.N. Ussachoff, Equation for the Importance of Neutrons, Reactor Kinetics and the Theory of Perturbation, In: Proc. 1st Intern. Conf. Peaceful Uses Atomic Energy, Geneva, Switzerland, 5, 503 (1955).
 
9. M. Arkani, et al., Prompt Neutron Decay Constant in Esfahan Light Water Subcritical Reactor (ELWSCR): Comparison of Rossi-α Experiment and Monte Carlo Simulation, Iranian Journal of Nuclear Science and Technology, 80, 18-24 (2017) (Published in Persian).
 
10. M. Arkani, et al., Measurement of prompt neutron decay constant of Esfahan light water subcritical reactor utilizing Feynman-α method, Iranian Journal of Nuclear Science and Technology, 76, 1-7 (2016) (Published in Persian).
 
11. K. Beckurts, Measurements with a Pulsed Neutron Source, Nuclear Science and Engineering, 2(4), 516 (1957).
 
12. E. Garelis, J.L. Russell Jr, Theory of pulsed neutron source measurements, Nuclear Science and Engineering, 16, 263 (1963).
 
13. D.B. Pelowitz, MCNPXTM 2.6.0, User´s Manual, Version 2.6.0, Los Alamos National Laboratory, LA-CP-07-1473 (2008).
 
14. Mathworks, MATLAB Reference Guide. The Mathworks Inc (2018).
 
15. A.F. Henry, Nuclear-Reactor Analysis, The MIT Press (1975).
 
16. T.B. Fowler, D.R. Vondy, G.W. Cunninghan, Nuclear reactor core analysis code-citation, USAEC, Report ORNL-TM-2496, ORNL-4078, ReV.2 (1971).
 
17. M. Zaker, Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor, Annals of Nuclear Energy, 30, Issue 15, 1591-1596, (2003).
 
18. S.C. Bailoche, MTR_PC Nuclear Engineering Division, INVAP, Argentina (2001).
 
19. C.M. Persson, et al., Pulsed neutron source measurements in the subcritical ADS experiment YALINA-Booster, Annals of Nuclear Energy, 35, 2357–2364 (2008).
 
20. TRR Safety Analysis Report, Safety Analysis Report for Tehran Research Reactor, Atomic Energy Organization of Iran (2011).
Journal of Nuclear Science, Engineering and Technology (JONSAT)
Volume 43, Issue 1 - Serial Number 99
January 2022
Pages 171-180

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