LWSCR Reactor Parameters Determination Based on Calculation and Experimental Results

Nassiri Mofakham, N; Nasr Azadani, Z; Sadeghzadeh, J

LWSCR Reactor Parameters Determination Based on Calculation and Experimental Results

Document Type : Research Paper

Authors

N Nassiri Mofakham

Z Nasr Azadani

J Sadeghzadeh

Abstract

This paper is dealing with the reactor parameter determination experiments performed at the light water subcritical reactor (LWSCR) in Esfahan. The parameter determination methods are derived from a theory based on neutron source position. The LWSCR reactor system is modeled by Monte Carlo calculations (MCNP4C), WIMSD5B and CITATION, and the criticality safety and neutron flux distribution problems are presented and analyzed. The analysis of the multiplication factors obtained by MCNP4C are in fairly good agreement with the results obtained by WIMSD5B and CITATION. For the flux distribution calculations, the MCNP4C results differ from the experimental observations by less than 12% and by ~5% for the WIMSD5B and CITATION.

Highlights

J.F. Briesmeister, editor, “MCNP-A general Monte Carlo N-particle trans-port code, version 4c, LA-13709-M,” Los Alamos National Laboratory, USA (2000).
M.J. Roth, “The preparation of input data for WIMS, 1967; M.J. Halsall, A summary of WIMSD4 input options, JEF-PC version 2, O.E.C.D., NEA Data Bank, France, (1997).

Experimental determination of material and geometrical buckling of ENTC sub-critical reactor, Experimental reactor physics group, Nuclear Engineering Department, Esfahan Nuclear Technology Center, Autumn (1369).

F.A. Valente, “A manual of Experiments in Reactor Physics,” McMillan-New York (1963).

J.R. Lamarsh, “Introduction to nuclear reactor Theory,” Addison-Wesley (1972).

Keywords

Light Water Sub-Critical Reactor

MCNP4C Code

WIMSD5B and CITATION Codes

Physical Parameters

J.F. Briesmeister, editor, “MCNP-A general Monte Carlo N-particle trans-port code, version 4c, LA-13709-M,” Los Alamos National Laboratory, USA (2000).
M.J. Roth, “The preparation of input data for WIMS, 1967; M.J. Halsall, A summary of WIMSD4 input options, JEF-PC version 2, O.E.C.D., NEA Data Bank, France, (1997).

Experimental determination of material and geometrical buckling of ENTC sub-critical reactor, Experimental reactor physics group, Nuclear Engineering Department, Esfahan Nuclear Technology Center, Autumn (1369).