The effectiveness of the water shield above the core and in the pool for shielding gamma rays
and neutrons was investigated by measurements and calculations for a tank-in-pool type reactor,
Ghana Research Reactor-1, GHARR-1. Experimental determination of y - dose rates were
made using Radiation Alert Monitor-4 and halogen counter type J613 y probe with readout on
y -radiation monitoring system of the control console and the microcomputer control system.
The PC version of the one-dimensional transport code ANISN was used to estimate the gamma
and the neutron dose-rates at various positions of the reactor. All computations were carried out
using the Sg angular quadrature in a cylindrical geometry pertaining to the reactor GHARR-1.
The P3 scattering order was assumed. The microscopic cross-sections of materials for various
regions were extracted from VITAMIN C master library consisting of 171 neutron and 36 photon
energies. Concentrations in various regions were computed based on procedures outlined in
WIMS-D/4. The calculational result of gamma dose rate was 25.8 fiSv / hr at the edge of the
pool for nominal power of 30kW which agreed with the experimental one of 25 juSv / h r . The
maximum and minimum percentage variation of the calculational and the experimental results
were 8.21 and 0.27 respectively with corresponding standard deviations of0.42 and 0.04. Based
on this satisfactory result, the dose profile along the slant tubes used to commission the reactor
was studied using the code and an assessment was also performed for the radiological
consequences of postulated accidents due to loss-of-coolant accidents. With the available
information on the variation of the neutron and the gamma doses along the slant tubes, high dose
theimolumniscent (TLD) badges could be used to confirm the calculated values in the future.
The tubes could then be mapped for studies on the effect of neutron and gamma irradiation on
mutation breeding of seeds in the field of agriculture. The effectiveness of the shielding in the
case of loss-of-coolant due to a break in the pipe of the reactor vessel or crack in the pool caused
by an earthquake was investigated. The results of the study indicate that the dose rates around
the reactor vessel and pool would be abnormally high. However, core melt-down is not expected
because the design features of the reactor are such that the core will remain covered with coolant
in the event of a break in a pipe line to the purification plant.
SSA, R (2021). Shielding Calculations For A Tank-In-Pool Reactor. Afribary.com: Retrieved April 16, 2021, from https://afribary.com/works/shielding-calculations-for-a-tank-in-pool-reactor
Research, SSA. "Shielding Calculations For A Tank-In-Pool Reactor" Afribary.com. Afribary.com, 08 Apr. 2021, https://afribary.com/works/shielding-calculations-for-a-tank-in-pool-reactor . Accessed 16 Apr. 2021.
Research, SSA. "Shielding Calculations For A Tank-In-Pool Reactor". Afribary.com, Afribary.com, 08 Apr. 2021. Web. 16 Apr. 2021. < https://afribary.com/works/shielding-calculations-for-a-tank-in-pool-reactor >.
Research, SSA. "Shielding Calculations For A Tank-In-Pool Reactor" Afribary.com (2021). Accessed April 16, 2021. https://afribary.com/works/shielding-calculations-for-a-tank-in-pool-reactor