Building the Nuclear and Radiological Safety and Security Authority in the Kingdom of Morocco: Sharing Experience and Lessons Learned

Following the example of several countries, the Kingdom of Morocco adopted, in the middle of the twentieth century, nuclear techniques in the medical and industrial fields, which have experienced a greater and sustained growth following its membership of the IAEA in 1957. This chapter presents the evolution of the nuclear and radiological infrastructure in Morocco over the last 60 years and the prospects for its future development. The chapter outlines the continuous efforts made by public authorities to upgrade the national nuclear and radiological regulatory framework in compliance with international obligations related to safety, security and safeguards. In this regard, the Moroccan Agency for Nuclear and Radiological Safety and Security (AMSSNuR) has, since its inception, been driven by the will and ambition to achieve its vision of establishing itself at the national level as an independent, effective, credible and transparent regulatory body; as well as a leader at the African level and significant contributor in the international arena. The Moroccan experience in safety and security governance and management is highlighted, and the lessons learned and experience gained in this area by AMSSNuR are shared.

Evaluation of the radiological risk in cargo scanning by comparison with known biological consequences

This study proposes a quick, easy, and low-cost method that can be used to assess the radiological safety of an irradiation line used for cargo and container inspection facilities. The radiation-emitting equipment used was a Smiths Heimam particle accelerator model HCVP4029 operating at 4.5 MeV. The radiation dose measurements were performed using a personal radiation monitor Ultra Radac mod MRAD 111 (Geiger–Muller). The ambient equivalent dose H*(10) was estimated for two facilities: A (real) (1.12E-03 mSv per scan) and B (fictitious) (3.25E-03 mSv per scan). The dimensionless factor R, which represents a ratio between two specific scanning (Ss) quantities regarding the facilities A and B, is introduced as a reference for assessing the level of radiological safety. This study compares facilities A and B by using a simple alternative safety assessment based on the R factor. The dimensionless R-value appears to be able to facilitate both the personnel’s and the general public’s perception of risk levels, even with no fixed scale.

Regulatory Requirements of Quality Assurance Program in Nuclear Medicine – Review of the Procedures

The quality assurance program ensures that the entire radiological system and associated equipment are functioning properly and optimally. To this end, it is essential that a quality assurance program be in place in each medical facility where ionizing radiation sources are used, to verify the proper functioning of these instruments as well as the radionuclides measured in nuclear medicine. In addition, the procedures of the quality assurance program must comply with regulatory requirements and international recommendations. The method of this study is to review the regulatory requirements adopted by different countries regarding the quality assurance program procedures as well as various recent scientific works and those published by the International Atomic Energy Agency. In addition, to compare the radiation protection requirements of the procedures of the mentioned works; exposure justification and optimization, quality control, registration system, professional training and audit system and to suggest improvements. The result of the review study, add a procedure to the quality assurance program, so that the quality assurance attempts to cover all procedures involving sources of ionizing radiation, thus ensuring compliance with the standards of radiological safety in nuclear medicine facilities.

Radiological Risk Assessment of Vehicle Transport Accidents Associated with Consumer Products Containing NaturallyOccurring Radioactive Materials

Natural and artificial ionizing radiation can be harmful to human health when they come into contact with people and the environment. Transport of naturally occurring radioactive materials (NORMs) and consumer products containing NORM in the public domain is inevitable owing to their potential applications. This study evaluates the dose and risk to the public from transport accidents of NORM and consumer products. Radiological and physical data were obtained from previous literature. The median and maximum values of radioactivity concentration were applied to consumer products and NORM data, which serve as an input. An external dose rate at 1 m from a transported shipment was calculated using MicroShield® Pro version 12.11 code, which serves as input to RADTRAN 6 code. Based on developed transport accident scenarios, a RADTRAN 6 code was used to estimate collective dose and risk. The sensitivity analysis was conducted by considering the variation of release, aerosol, and respirable fractions of radionuclides at 0.1%, 1%, 10%, and 100% from the transported shipment during an accident, respectively. The results of dose and risk to the general public because of the damage of the shipment container following a fire accident are below the annual regulatory limits of 1 man-Sv recommended by IAEA transport regulation of 2018. The sensitivity results of all NORMs and associated consumer products are also below the regulatory limits. Therefore, radiological safety can be ensured in the event of a transport accident involving the transit of NORM and consumer products containing NORM.

Sassi of Matera Building Material: High-Resolution Gamma-Ray Spectroscopy Characterization for Radioprotection

The Sassi of Matera (Basilicata region, southern Italy) is a peculiar site, but not unique in Italy, from a landscape point of view. Most of the buildings are excavated in rocks of calcarenite origin and used as homes and accommodation facilities. For this reason, the contribution of gamma radiation to the population due to this building material has been investigated for the first time. Even though the type of rock is not mentioned among the construction materials indicated in Italian Legislative Decree 101/2020 to be subjected to radiological characterization, the methodology indicated in the decree was applied, comparing the values with those present in the literature. The content of 226Ra, 232Th and 40K was then investigated with gamma spectroscopy, and the gamma index was calculated. The results obtained showed a low level of activity concentration of natural radionuclides in this type of stone, confirming the radiological safety. This result can also support the recovery and restoration initiatives for these buildings to conserve the architectural and landscape heritage of this village.

Determination of Natural Radioactivity and Radiological Hazard Associated with Sediments Sourced from Ogunpa River Channels, Ibadan, Nigeria

The natural radionuclides content and radiological assessment of sediments of the Ogunpa waste-water channel were evaluated to ascertain the radiological safety of the sediments as a building material. The mean activity concentrations of 40K, 226Ra and 232Th in Bq kg−1 were found to be 171 ± 69, 11 ± 5 and 10 ± 4, respectively. The overall mean radium equivalent 29 ± 13 Bq kg−1 was <370 Bq kg−1 that can give the maximum recommended dose of 1 mSv to the general public. The activity concentrations of the radionuclides were all less than world average for soils and sediments. Thus, the use of the sediments from the Ogunpa water channel as building material is safe and would not pose any significant radiological health hazards.

An unknown source of reactor radionuclides in the Baltic Sea revealed by multi-isotope fingerprints

We present an application of multi-isotopic fingerprints (i.e., 236U/238U, 233U/236U, 236U/129I and 129I/127I) for the discovery of previously unrecognized sources of anthropogenic radioactivity. Our data indicate a source of reactor 236U in the Baltic Sea in addition to inputs from the two European reprocessing plants and global fallout. This additional reactor 236U may come from unreported discharges from Swedish nuclear research facilities as supported by high 236U levels in sediment nearby Studsvik, or from accidental leakages of spent nuclear fuel disposed on the Baltic seafloor, either reported or unreported. Such leakages would indicate problems with the radiological safety of seafloor disposal, and may be accompanied by releases of other radionuclides. The results demonstrate the high sensitivity of multi-isotopic tracer systems, especially the 233U/236U signature, to distinguish environmental emissions of unrevealed radioactive releases for nuclear safeguards, emergency preparedness and environmental tracer studies.

Development of the digital twin to assess current radioecological situation inside the 30-km zone in the area of Pilot demonstration energy complex (PDEC) siting

The development of the digital twin for the assessment of current radioecological situation is considered in the paper. For the twin development data of comprehensive radioecological survey in the area of the Pilot demonstration energy complex (PDEC) siting were used. The twin was de-veloped with the use of the ArcMap 10.5 software module, the part of the ArcGis package. The digital twin is a virtual model that describes the real-time radioecological situation inside the 30-km zone of the nuclear object influence using a set of mathematical models and maps. The twin contains information on radionuclides and heavy metals content in the environment, radiation doses to humans and biota. The data contained in the twin were used for preparing and publish-ing the atlas of the radioecological situation in the 30-km zone of PDEC influence. The results ob-tained can be used for radiological safety assessment and optimization of radiation monitoring programs for PDEC.