Radioactive dispersion analysis for hypothetical nuclear power plant (NPP) candidate site in Perak state, Malaysia

Abstract

Abstract. Malaysia is planning to build a nuclear power plant (NPP) by 2030 to diversify the national electricity supply and resources. Selection of an NPP site must consider various factors, especially nuclear safety consideration to fulfil the nuclear safety objectives. Environmental Risk Assessment Analysis is a part of safety requirements by the International Atomic Energy Agency (IAEA) prior to the NPP commissioning process. Risk Assessments Analysis (RIA) is compulsory for the NPP site evaluation. One of RIA methods are Radioactive Dispersion Analysis using probabilistic risk analysis software. It is also important to perform studies to estimate the impact to the neighbouring population in the case of a nuclear accident at the power plant. In the present work, aimed to study the impact of a hypothetical nuclear accident by simulating the dispersion pattern of radionuclides originated from a candidate site at Manjung, Perak. The work has been performed using the HotSpot Health Physics codes. Two types of radionuclides have been considered namely I at major towns in Perak such as Lumut and Sitiawan are 1.2 mSv and 9.9 mSv. As for Taiping, Ipoh, Kampar, and Teluk Intan the estimated TEDE is around 0.2 mSv and 1.6 mSv respectively. In conclusion, the dispersion can reach as far as 80 km from the site. However, estimated annual effective dose is not more than 1 mSv limit, which is considered acceptable in the point of view of radiological health risk for human and the environment.

Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh

“…( 7) [31]: The Gaussian diffusion factor F can be evaluated by applying the 22.5 o sector averaged form of the GPM for a defined value of H eff as follows in Eq. ( 8): (8) Here, denotes the diffusion parameter (m) in vertical direction.…”

“…In case of a radiological accident, studies of atmospheric dispersion and assessment of radiological dose are crucial for regulators to prepare emergency response plans [5][6][7]. Analysis of radiological safety for postulated accidents allows a dominant input for safety assessment of nuclear reactors considering the safety of occupational workers and the general public [8][9][10][11][12][13][14][15][16][17][18][19]. The TRIGA research reactor was licensed on the condition that there will be no significant hazard or undue radiation effect on human health and safety as the reactor becomes a source of intense ionizing radiation during its operations [20][21][22][23].…”

The Study of Atmospheric Dispersion Model on Accident Scenario of Research Reactor G. A. Siwabessy Using Hotspot Codes as a Nuclear Emergency Decision Support System

“…One of the simplest software is HotSpot Health Physics Codes developed by National Atmospheric Release Advisory Center (NARAC). This software applies a conservative and low range Gaussian plume model (less than 10 km) [10][11][12][13][14][15][16].…”

Simulation and calculation of power plant accidents doses using HotSpot software

“…There are main and important factors that determine the rate and severity of release [6]. However, there are several numbers of radionucleotides contribute a great role in the possible incident.…”