Published April 2021 | Version v1
Journal article

Determination of Reactor Parameters for Different Subcritical Configurations of the Philippine Research Reactor-1 TRIGA Nuclear Fuel

  • 1. Science Education Institute Department of Science and Technology Bicutan, Taguig City 1631 Philippines (Philippines)
  • 2. Nuclear Reactor Operations Section Philippine Nuclear Research Institute Department of Science and Technology Quezon City 1101 Philippines (Philippines)

Description

The Philippine Research Reactor-1 (PRR-1) will be revived as a subcritical assembly for training, education, and research (SATER) in the field of nuclear science and technology. SATER will utilize the existing slightly irradiated nuclear fuel rods that have been maintained in the PRR-1 facility for more than 30 years. A subcritical arrangement for the fuel rods was chosen considering the inherent safety of this configuration. In this paper, we calculate relevant reactor parameters that characterize different annular and hexagonal subcritical configurations of 44 PRR-1 fuel rods. These parameters include the neutron multiplication factor keff the effective delayed neutron fraction βeff and the mean neutron generation time λ, which are essential quantities to describe reactor behavior. Calculations were performed using the well-validated Monte Carlo radiation transport code MCNP5 v.1.6 together with the ENDF/BVII. 1 evaluated nuclear data library. The maximum keff value is 0.96735 ± 0.0003 at 4.3 cm pitch for the chosen hexagonal arrangement. For these configurations, the reactor kinetic parameters were βeff=756 ± 4pcm and λ = 41 μs for the annular arrangement, while βeff = 460 ± pcm and λ = 40 μs for the hexagonal arrangement. Results demonstrate that with 44 fuel rods, different fuel arrangements remain subcritical with a subcriticality margin that is at least 3% Δk/k or maximum keff of 0.97. The key reactor performance characteristics determined in this study can aid in the analysis of transient behavior and safety assessment of subcritical core configurations with TRIGA fuel rods. Our results provide support in expanding the utilization options for irradiated TRIGA fuel rods, even for other TRIGA facilities. (authors)

Additional details

Identifiers

Publishing Information

Journal Title
Philippine Journal of Science
Journal Volume
150
Journal Issue
2
Journal Page Range
p. 453-460
ISSN
0031-7683

Optional Information

Notes
refs., 1 tab., 6 figs.