Modeling and Validation of Temperature and Void Effects on Reactivity Experiments at the Missouri S&T Research Reactor
To validate an MCNP5 model of the Missouri S&T Research Reactor (MSTR), temperature and void effects on reactivity experiments were simulated and performed. We compared the keff of the modeled reactor mirroring the position of all control rods to the actual critical reactor (keff = 1.00000). In the simulation we modeled three different scenarios. In the first two scenarios, the reactor is modeled as isothermal at two different temperatures (measured experimentally near the core), and in the third scenario, we split the core into bottom and top parts and used interpolated values for the temperatures of both halves. The model predicted keff's for the "critical reactor" between 1.00234 and 1.00248 (±0.00018) when using as temperature the experimental thermocouple readings at the top of the core and keff's between 1.00296 to 1.00383 (±0.00018) when using the temperature of thermocouple readings at the bottom of the core. In the third experiment, a linear vertical temperature profile was included in the model (only top and bottom of the core), and the model predicted keff's between 1.00218 and 1.00302 (±0.00018). The keff modeled and experimental values differed by as much as 0.40%. A void coefficient of the reactivity experiment was also simulated introducing a void tube in the model and the control rods made to mirror the critical experimental reactor with an identical void.
B. Richardson et al., "Modeling and Validation of Temperature and Void Effects on Reactivity Experiments at the Missouri S&T Research Reactor," Nuclear Science and Engineering, vol. 187, no. 1, pp. 100-106, American Nuclear Society (ANS), Jul 2017.
The definitive version is available at https://doi.org/10.1080/00295639.2017.1292089
Nuclear Engineering and Radiation Science
Keywords and Phrases
MCNP; Missouri S&T nuclear research reactor; Void coefficient of reactivity
International Standard Serial Number (ISSN)
Article - Journal
© 2017 American Nuclear Society (ANS), All rights reserved.
01 Jul 2017