Research Article 
								Modified CANDU Reactor MCR as an Early-Deployable Nuclear Workhorse
								
									
										
											
											
												Jürgen Knorr* ,
											
										
											
											
												Albert Kerber
,
											
										
											
											
												Albert Kerber
											
										
									
								 
								
									
										Issue:
										Volume 9, Issue 3, September 2024
									
									
										Pages:
										51-60
									
								 
								
									Received:
										2 September 2024
									
									Accepted:
										4 October 2024
									
									Published:
										29 October 2024
									
								 
								
								
								
									
									
										Abstract: Safe, simple and soon deployable are the imperatives for each SMR concept today. Only this SMR has the potential to become a nuclear workhorse in the fight against climate change if it is available soon, in large numbers and deployable worldwide. Therefore the assessment of the usefulness of an SMR concept must not only relate to the reactor itself. Only a holistic view of the entire nuclear fuel cycle with the given SMR as the central part between the front-end and back-end can lead to viable decisions. The IAEA lists more than 120 SMR concepts in its Handbook 2022. Time pressure is forcing us to critical selection of a promising reactor concept and to combine innovative solutions with tried and established technical and administrative networks. Against this background, the Modified CANDU Reactor (MCR) is proposed as additional SMR design. The MCR has two obvious modifications compared to the well-known and globally proven CANDU design: a) spherical fuel elements (pebbles) with ceramic cladding b) vertical arrangement of the pressure tubes. Intended for the generation of heat and electricity close to the consumer, the construction of a plant with MCR is preferably carried out underground close to the surface. The Herrenknecht VSM-shaft-tunnel technology is planned for the construction of the structures. For the transportation of irradiated fuel elements, (extended) interim storage and final disposal, technologies are proposed (Initial Barrier; TRIPLE C) that have already been published elsewhere. In order to provide a basis for further scientific and technical discussions, an attempt was made to incorporate the MCR concept into the existing CANDU SMR TM design. The resulting combined “overlapping” concept has not yet been discussed with the CANDU developing and operating countries. The authors hope for a fruitful discussion and are looking for future cooperation with the CANDU SMR TM manufacturer (CANDU Energy Inc. Canada), as well as with the countries that traditionally use CANDU reactors (China, India, South Korea) and Norway in future maybe too.
										Abstract: Safe, simple and soon deployable are the imperatives for each SMR concept today. Only this SMR has the potential to become a nuclear workhorse in the fight against climate change if it is available soon, in large numbers and deployable worldwide. Therefore the assessment of the usefulness of an SMR concept must not only relate to the reactor itself...
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								Research Article 
								Radiological Health Risk of Exposure to Gamma Radiation in Private Diagnostic Center in Khana Local Government Area Rivers State, Nigeria
								
									
										
											
											
												Nwii Abayiga Abel*,
											
										
											
											
												Biibalo Livinus Legborsi*
											
										
									
								 
								
									
										Issue:
										Volume 9, Issue 3, September 2024
									
									
										Pages:
										61-70
									
								 
								
									Received:
										2 July 2024
									
									Accepted:
										1 August 2024
									
									Published:
										13 November 2024
									
								 
								
								
								
									
									
										Abstract: The In-situ measurement of background ionizing radiation of Centre of Life hospital Bori in Khana Local Government Area of Rivers state of Nigeria has been carried out. Digilert-200 Radiation meters was utilized in measurement of background ionizing radiation and Global Positioning System (Garmin 765) was used in measuring coordinates of the sampling points. Fifteen (15) sampling points were arbitrarily selected within the diagnostics centre. The results of the BIR outdoor and indoor varies from 0.010 - 0.015 with mean of 0.013 mRhr-1. Absorbed Dose rate varies from 87.0 -130.5 nGy/yr with mean of 114.3 nGy/yr and 116.0 nGy/yr for outdoor and indoor. AEDE varies from 0.107 – 0.160 with mean of 0.140 mSv/yr and 0.142 mSv/yr and Excess life cancer risk varies from 0.37×10-3 – 0.56×10-3 with mean of 0.50×10-3 and 0.50×10-3 for outdoor and indoor respectively. The obtained values for BIR of Centre of Life Hospital Ltd was within recommended standard limit of 0.013mR/h. The obtained result for AEDE was within the recommended safe limit. The obtained results of ELCR and the ADR are all higher than the recommended standard of 0.29 x 10-3 and 84.0 nGy/h respectively. The result of radiation dose to different body organ shows that the testes have the highest radiation percentage for outdoor and indoor respectively.
										Abstract: The In-situ measurement of background ionizing radiation of Centre of Life hospital Bori in Khana Local Government Area of Rivers state of Nigeria has been carried out. Digilert-200 Radiation meters was utilized in measurement of background ionizing radiation and Global Positioning System (Garmin 765) was used in measuring coordinates of the sampli...
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