Study of Fuel Rods Axial Enrichment Distribution Effect on the Neutronic Parameters of the Reactor Core

Pazirandeh, A; Nasiri, S.H

Study of Fuel Rods Axial Enrichment Distribution Effect on the Neutronic Parameters of the Reactor Core

Document Type : Research Paper

Authors

A Pazirandeh

S.H Nasiri

Abstract

Optimization of the fuel burn up is an important issue in nuclear reactor fuel management and technology. Radial enrichment distribution in the reactor core is a conventional method and axial enrichment is constant along the fuel rod. In this article, the effects of axial enrichment distribution variation on neutronic parameters of PWR core are studied. The axial length of the core is divided into ten sections, considering axial enrichment variation and leaving the existing radial enrichment distribution intact. This study shows that the radial and axial power peaking factors are decreased as compared with the typical conventional core. In addition, the first core lifetime lasts 30 days longer than normal PWR core. Moreover, at the same time boric acid density is 0.2 g/kg at the beginning of the cycle. The flux shape is also flat at the beginning of the cycle for the proposed configuration of the axially enrichment distribution.

Highlights

Christopher M. Regan, “US Nuclear Regulatory Commission, Certificate of compliance for radio-active material package No. 9297 and 2nd Revision,” Issued to Westinghouse Electric Company, Dec.27 (2006).
C.J. Taubman, “The WIMS 69-group library tape 166259,” AEEW-M1324 (1975).

T.B. Fowler, D.R. Vondy, G.W. Cunningham, “Nuclear Reactor Core Analysis Code: Citation-Ldi2 ORNL,” Rev. 2 (July 1971).

S.M. Bowman, I.C. Gauld, J.C. Wagner, “Recommendations on fuel parameters for standard technical specifications for spent fuel storage casks,” NUREG/C-6716 ORNL/Tm-2000/385 (Mar 2000).

J.C. Wagner, C.V. Parks, “Impact of burnable poison rods on PWR burnup credit criticality safety analyses,” Trans. Am. Nucl. Soc. 83, 130-134, (Nov 2000).

J.C. Wagner, “Criticality analysis of assembly misload in a PWR burnup Credit Cask,” NUREG/CR-6955, ORNL Tan (2008).

Keywords

Nuclear Fuel Enrichment

Fuel Management

Power Peaking Factor

Axial Enrichment

Christopher M. Regan, “US Nuclear Regulatory Commission, Certificate of compliance for radio-active material package No. 9297 and 2nd Revision,” Issued to Westinghouse Electric Company, Dec.27 (2006).
C.J. Taubman, “The WIMS 69-group library tape 166259,” AEEW-M1324 (1975).

T.B. Fowler, D.R. Vondy, G.W. Cunningham, “Nuclear Reactor Core Analysis Code: Citation-Ldi2 ORNL,” Rev. 2 (July 1971).

S.M. Bowman, I.C. Gauld, J.C. Wagner, “Recommendations on fuel parameters for standard technical specifications for spent fuel storage casks,” NUREG/C-6716 ORNL/Tm-2000/385 (Mar 2000).

J.C. Wagner, C.V. Parks, “Impact of burnable poison rods on PWR burnup credit criticality safety analyses,” Trans. Am. Nucl. Soc. 83, 130-134, (Nov 2000).