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ENVIRONMENTAL RADIOLOGY AND QUALITY ASSURANCE FOR NPP SITE SELECTION
Full text linkENVIRONMENTAL RADIOLOGY AND QUALITY ASSURANCE FOR NPP SITE SELECTION. This research briefly explains environmental radiology and quality assurance for NPP sites compiled from regulations, standard documents, and national and international literature. The selection of sites on the coast needs to be performed through research concerning local meteorological conditions with radioactive elements distributed to humans and the surrounding environment through the air and water body. Environmental radiology measurements and monitoring need to be programmed and implemented starting from the initial stage of site selection to the decommissioning. Quality assurance programs for sample measurements and environmental radiology have to be established to ensure the validity of measurement results and have to be reviewed and verified by independents which indirectly involved in measurement and research
THE VERIFICATION OF THE RSG-GAS REACTOR COOLING TOWER HEAT TRANSFER CAPACITY
Full text linkThe RSG-GAS reactor has been replaced and the technical specifications for the new cooling tower specify that the heat transfer capacity from the secondary cooling water to the environment is 5500 kW per module. Therefore, this study aims to verify the theoretical calculations of the heat transfer capacity using performance test data collected on the 30 MW power operation on December 20, 2018, such as the temperature of the primary and secondary coolant entering and exiting the cooling tower, wet bulb, and environmental dry bulb temperature, as well as the inlet and outlet air temperature. Furthermore, the data were used to calculate the heat transfer capacity from the secondary cooling water to the environment. The results showed that each cell of the RSG-GAS cooling tower reactor transfers the heat of approximately 5528.52 kW. This value is consistent with the technical specifications written in the revised RSG-GAS Safety Analysis Report 11
POTENTIAL OF RICE STRAW AS A NATURAL FIBER MATERIAL FOR COMMERCIAL PRODUCTS
No full textCellulose is a material used in producing natural fibers, which is more environmentally friendly than synthetic fibers.Rice straw waste contains much cellulose and has potential as natural fiber.However, before the natural cellulose fiber is extracted from the rice straw, it must pass through several processes, such as chemicals or nuclear radiation, especially during the pretreatment process. Furthermore, the resulting natural fibers are utilized to replace synthetic fibers for use as raw materials in manufacturing several commercial products. This review describes a process that can be applied to manufacture natural fibers from rice straw and commercial products made from natural cellulose fibers.Cellulose is a material used in producing natural fibers, which is more environmentally friendly than synthetic fibers. Rice straw waste contains much cellulose and has potential as natural fiber. However, before the natural cellulose fiber is extracted from the rice straw, it must pass through several processes, such as chemicals or nuclear radiation, especially during the pretreatment process. Furthermore, the resulting natural fibers are utilized to replace synthetic fibers for use as raw materials in manufacturing several commercial products. This review describes a process that can be applied to manufacture natural fibers from rice straw and commercial products made from natural cellulose fibers
Intercomparison of Gamma Cell 220 Irradiator Facilities and Dr. Mirzan T Razzak Gamma Irradiators Using Harwell Dosimeters
Full text linkThe gamma irradiator is a multi-purpose facility that possibly used to preserve food, sterilize medical equipment, and conduct genetic engineering and polymerization processes, during which the absorbed dose of the product is critical. The standardization of product quality assurance was regulated by the IAEA Technical Document Number 409 considering Dosimetry for Food Irradiation and ISO 14470 and 11137-3 on Food Irradiation, as well as the Guidance on Dosimetric Aspects of Development, Validation, and Routine Control, respectively. The absorbed dose was influenced by the movement of the product to the source, its position, the amount of radioactive activity in the facility, and the dose rate in the irradiation room. The dosimeter performance test and quality assurance of the system were conducted using the Facility Intercomparison Technique which tested the dosimeter (measuring instrument) at 2 different facilities to determine the performance of the measuring instrument.. In this study, 2 irradiation facilities were tested using a Harwell routine dosimeter in the dose range of 1 kGy to 30 kGy and 20 dose points. The results showed that the highest deviation reached 19% and 21% at the Gamma Cell 220 and the Dr. Mirzan T Razzak Gamma irradiator facilities. This elevated the performance of the dosimeters to determine the precision accuracy of the dose-measuring instrument
Evaluation of The Officer’s Behaviour in Public Services of The Nuclear Minerals Technology
No full textService behaviour is defined generally as service behaviour that refers to official job descriptions and service scripts and completes core service tasks using standard service procedures. Evaluation of the behaviour of service officers has the opportunity to trigger continuous improvement in service quality to improve organizational performance—primary data from 73 questionnaires, which are the result of customer satisfaction assessment of nuclear mineral technology services. Data analysis used descriptive frequency statistics that provide a typical condition of the diversity of data. The behavioural evaluation results show that service personnel is polite, not selective; all customers have the same position, officers complete services according to the agreed period, officers complete services following service requirements. This research provides evidence that uncertainty in serving customers requires frontline employees to take personal initiative to anticipate customer needs, prevent and eliminate potential obstacles in service delivery, and continuously identify new opportunities to improve service quality
DESIGN OF DECY-13 CYCLOTRON DAQ SYSTEM
Full text linkPSTA BATAN (Center of Science and Accelerator Technology) has been developed the 13 MeV cyclotron named DECY-13 for producing radioisotope. That cyclotron has five subsystems and hasn’t established by communication standard protocol yet. In order to make cyclotron communicate effectively, this paper presented the design of data acquisition with OPC (OLE for Process Control) based standard protocol and it has established in DECY-13’s Instrumentation and Control System by case study method. We used Modbus TCP/IP architecture to make all of HMI from five subsystems building communication with each other to Server Computer (OPC Server). OPC Server and OPC Client has configured by NI OPC Server and NI LabVIEW. Data acquisition has monitored by LabVIEW. Configuration of the system for 13 MeV cyclotron and performance test result showed in RMSE value from Reflected Drive Amp Power is 13,94 %, Magnetic Field is 11,2 % ; Forward Final Amp Power is 5,24 % ; Forward Drive Amp Power is 1,98 % ; MPS current is 1,87 % ; Beam Current and A2 Sensor are 1,85 % ; B2 Sensor is 1,77 % ; Bias Current is 1,71%. Based on monitoring and test result, the design of DAQ system has succeeded and established the communication from several different data types from subsystems with OPC protocol standar
VERIFICATION OF THE DETERMINATION OF 12 MEV ELECTRON BEAM OUTPUT VERSA HD / 154714 LINEAR SPEEDING PLANE IN MAYAPADA HOSPITAL
No full textVERIFICATION OF THE DETERMINATION OF THE NOMINAL ENERGY BEAM OUTPUT OF THE 12 MEV LINEAR ACCELERATOR PLANE ELEKTA VERSA HD / 154714 AT MAYAPADA HOSPITAL. This paper describes verifying the determination of the 12 MeV nominal energy beam electron water absorption dose emitted from the Elekta Versa HD / 154714 medical linear accelerator owned by Mayapada Hospital, Lebak Bulus, Jakarta. Measurements were done in the 1D water phantom Scanner under reference conditions with the distance of the radiation source to the surface of the water 100 cm and the radiation field formed by the applicator 10 cm x 10 cm and the depth corresponding to (0.6 R50 - 0.1) cm. The IBA CC13 ionization detector is used as a radiation measurement tool for PDD measurements, while the Roos parallel ionization detector is used for absolute measurements. Roos's parallel ionizer detector is aligned with PTKMR-BATAN's PTW Webline electrometer. This detector is also traced to the primary standard laboratory of BIPM, France. Meanwhile, the PCC04 chip ionizing detector parallel to the PCC04 is coupled with a Dose 1 electrometer owned by Mayapada Hospital, which is traced to the PTB primary standard laboratory. Calculation of measurement results is carried out using the IAEA dosimetry protocol contained in Technical Report Series No. 398. The results obtained indicate a fairly good fit between the two measurements with a difference of 0.3
ANALYSIS OF HEAT AND MASS TRANSFER ON COOLING TOWER FILL
Full text linkThis paper discusses heat and mass transfer in cooling tower fill. In this research, dry bulb temperature at the bottom fill, ambient relative humidity, air stream velocity entering fill, dry bulb temperature leaving the fill, relative humidity of air leaving the fill, inlet and outlet water temperature of cooling tower were measured. Those data used in heat and mass transfer calculation in cooling tower fill. Then, do the heat and mass transfer calculation based on proposed approch. The results are compared with design data. The design and analogy method showed different result. The parameter which influence the heat transfer at cooling tower are represented by coefficient of heat transfer hl and coefficient of mass transfer kl. The differencies result between design and analogy method shows that there is important parameter which different. Deeply study needed for it
An Analysis of Radiation Worker Safety at SAMOP Facility PSTA-BATAN Yogyakarta Using MCNP6
Full text linkIt has been done the calculation of g dose simulation received radiation worker around SAMOP using MCNP6. The fuel SAMOP was modelled on the solution of uranyl nitrate (UO2(NO3)2) with enrichment of 19.75% and a concentration of 300 g U/L. SAMOP was operated on a power of 600 watts and burn up for 6 days using ORIGEN2. From the simulation burn up acquired information g radiation contribution used to calculate the dose received by radiation workers. The Calculation of the dose rate using MCNP6 at a distance of 225 cm from SAMOP without shielding obtained the result of g dose the amount of (11,217.39 ± 0.35) mSv/hour with the estimated working time of radiation workers at 0.02 hours/week. Addition of the barite concrete shielding with a thickness of 47.69 cm at a distance of 225 cm from SAMOP using an extrapolation approach based on the variation of the shielding thickness of simulation calculation results obtained g dose rate of 5.21 mSv/hour and estimated time maximum work of 36.98 hours/week
Probability study of airplane crash on Kartini Reactor site area
No full textAbstract. Probability study of airplane crash at Kartini Reactor site has been carried out. Objective of this study is to determine probability of airplane crash coming from airports around Kartini Reactor site to Kartini Reactor Site. This study was carried out in several stages, namely identification of airports around Kartini Reactor site, initial screening using SDV values (10 km for small airport and 16 km for large airport), probability calculation of airplane crash at Kartini Reactor site and comparing the calculation result with applicable regulations. Based on the identification results there are four airports / runways around the Kartini Reactor site, they are Adi Sutjipto Airport, Adi Sumarmo Airport, Depok Runway, and Yogyakarta International Airport where distance from airport to the site between 2.26-48.23 km. After screening using SDV value, that is known only Adi Sutjipto Airport which is inside SDV radius of Kartini Reactor, so that probability of airplane crash from Adi Sutjipto Airport is calculated, i.e. 3,769x10-8 events/year is. This value is still under the provisions in BAPETEN Regulation No. 4 of 2018 i.e. maximum 10-7 events/year. So it can be concluded that Kartini Reactor is safe from the possibility of airplane crash