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Adoo, N.A, Nyarko, B.J.B., Akaho, E.H.K., Alhassan, E., Agbodemegbe, V.Y., Bansah, C.Y. and Della. R. (2011) Determination of Thermal Hydraulic Data of GHARR-1 under Reactivity Insertion Transients Using the PARET/ANL Code. Nuclear Engineering and Design, 241, 5203-5210.
https://doi.org/10.1016/j.nucengdes.2011.09.019

has been cited by the following article:

• TITLE: Transient Studies of Ghana Research Reactor-1 after Nineteen (19) Years of Operation Using PARET/ANL Code

  AUTHORS: Bright Madinka Mweetwa, Emmanuel Ampomah-Amoako, Edward Horga Korbla Akaho

  KEYWORDS: Reactivity Insertion, Transients, Control Rod Worth, Power Peaking Factor, Moderator Reactivity Coefficient, Neutronic Parameters

  JOURNAL NAME: World Journal of Nuclear Science and Technology, Vol.7 No.4, August 10, 2017

  ABSTRACT: The Program for the Analysis of Reactor Transients/Argonne National Laboratory (PARET/ANL) code was used to predict the thermal hydraulic behaviour of the Ghana Research Reactor-1 after adding 9.0 mm of beryllium to the top shim tray of the core. The core was analysed for reactivity insertions 2.1 mk, 3.0 mk, 4.0 mk, 5.0 mk and 6.7 mk, respectively. The reactor is still safe to operate in the range 2.1 mk to 4.0 mk. However, 2.1 mk would be ideal since the reactor automatic shutdown (SCRAM) is set not to exceed 120% of reactor nominal power.