Investigation on the group constants of the HEU and LEU fuel cell type VVR-M2

Authors

  • Do Quang Binh Trường Đại học Sư phạm Kỹ thuật TP.HCM, Việt Nam
  • Vo Thanh Tan Trường Đại học Sư phạm Kỹ thuật TP.HCM, Việt Nam
  • Ngo Quang Huy Trường Đại học Công nghiệp Tp HCM
  • Nguyen Hoang Hai Trung tâm Nghiên cứu & Triển khai Công nghệ bức xạ Tp HCM

Corressponding author's email:

binhdq@hcmute.edu.vn

Keywords:

VRR-M2, HEU, LEU

Abstract

This paper presents the evaluated results of fuel cell group constants for the VVR-M2 HEU and VVR-M2 LEU fuels loaded in the Dalat nuclear research reactor. The dependence of the group constants on the fuel burn up was also investigated. These results are the important data served for the global reactor core calculations with HEU and LEU fuels. The calculations were done by the multi group neutron transport theory with the WIMS code.

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References

L. B. Vien, L. V. Vinh, H. T. Nghiem, N. K. Cuong, Neutronics and thermal hydraulics analysis for full core conversion of the Dalat nuclear research reactor, Proceedings of the 9th National conference on Nuclear science and technology, Science and Technics Publishing House, 175-187 (2011).

AEA Technology, WIMSD – A neutronics Code for Standard Lattice Physics Analysis, ANSWERS Software Service (1997).

Halsall, M.J., C.J. Taubman, C.J., 1986. The ‘1986’ WIMS Nuclear Data Library, AEEW-R 2133, AEE Winfrith.

G. I. Bell and S. Glasstone, Nuclear Reactor Theory, Van Nostrand Reinhold Company, New York (1970).

Published

28-08-2013

How to Cite

[1]
Đỗ Quang Bình, Võ Thanh Tân, Ngô Quang Huy, and Nguyễn Hoàng Hải, “Investigation on the group constants of the HEU and LEU fuel cell type VVR-M2”, JTE, vol. 8, no. 2, pp. 84–92, Aug. 2013.