Usulan kriteria pemulangan pasien (patient release) kedokteran nuklir di Indonesia

Nuclear medicine procedures are carried out by applying a radioactive substance to the patient’s body. Thus, the patient can be assumed to be a ‘radiation source’ and needs to follow special provisions so that his presence does not expose nearby individuals unnecessarily. Therefore, when the patient is released from the hospital, it must ensure that the patient’s radiation exposure does not expose the individuals in the vicinity. However, several related regulations have not regulated this in detail. In this paper, a study is carried out regarding the criteria considered in the release of nuclear medicine patients. The method used is a literature study. The study results recommend release criteria through two approaches based on the estimated maximum effective dose that the public may accept, namely conditional release with a calculated dose of less than or equal to 5 mSv and unconditional release with an estimated dose of less than or equal to 1 mSv. Conditional release is the release of a patient provided with post-release guidance, while unconditional release is the release of the patient without being supplied with post-release advice. Keywords: nuclear medicine, patient release, conditional release, unconditional release

Visualization of Radioactive Substances Using a Freely Moving Gamma-Ray Imager Based on Structure From Motion

Technology for measuring and identifying the positions and distributions of radioactive substances is important for decommissioning work sites at nuclear power stations. A three-dimensional (3D) image reconstruction method that locates radioactive substances by integrating Structure-from-Motion (SfM) with a Compton camera (a type of gamma-ray imager) has been developed. From the photographs captured while freely moving in an experimental environment, a 3D structural model of the experimental environment was created. By projecting the radioactive substance image acquired by the Compton camera on the 3D structural model, the positions of the radioactive substance were visualized in 3D space. In a demonstration study, the 137Cs-radiation source was successfully visualized in the experimental environment captured by the freely moving cameras. In addition, how the imaging accuracy is affected by uncertainty in the self-localization of the Compton camera processed by SfM, and by positional uncertainty in the gamma-ray incidence determined by the sensors of the Compton camera was investigated. The created map depicts the positions of radioactive substances inside radiation work environments, such as decommissioning work sites at nuclear power stations.

BAPETEN SUPERVISORY AUTHORITY IN THE PROCEDURE OF TRANSPORTATION OF RADIOACTIVE SUBSTANCE THROUGH THE SEA

<em>One important thing that must be considered in the use of nuclear and other radioactive materials is the process of transporting radioactive substances through the sea. This paper will analyze the optimization of the supervisory authority of BAPETEN in the transportation of radioactive substances, especially in the process of transporting radioactive substances by sea. Option to choose the sea because most of Indonesia's territory is the sea. If it has the authority, Bapeten's supervisory authority will then be analyzed in the process of transporting radioactive substances via the sea lane. Recommendations from this article are a form of juridical liability if an error occurs, which causes a loss in the process of transporting radioactive substances by sea. Because the process of transporting radioactive substances is essential in preventing the occurrence of radiation, the regulatory authority in the transportation process must be regulated in detail based on the precautionary principle, as well as the form of juridical accountability.</em>

Numerical simulation on aerosol pool scrubbing

In the event of severe accident for nuclear power plant (NPP), radioactive aerosols may be released into spent fuel pool (SFP) through filtered-containment-venting-system (FCVS), which are entrained by mixing gas from containment, in order to prevent the overpressure of containment. The efficiency of aerosol pool scrubbing determines the radioactive threats of spent fuel compartment induced by containment venting, and the probable amount of radioactive substance during atmospheric dispersion later on. Therefore, it is necessary to study the typical flow phenomena during the process of aerosol pool scrubbing in the SFP of PWR nuclear power plants, and figure out the important regularities and mechanisms, which can provide reference for evaluations of radioactive threats of spent fuel compartment and provide technical supports for new type of designs for SFP and venting system. In this paper, Fluent is used to establish two kinds of numerical models of SFP, including horizontal injection and vertically downward injection configurations, according to the geometrical dimensions of Qinshan 2 NPP’s SFP. TiO2 is used as the substitute of radioactive substance and coupled numerical models of VOF and DPM are introduced for qualitative and quantitative studies on the effects of diameter of aerosol particle, injection velocity, initial water depth and injection direction. The decontamination factor (DF) is determined by quantifying the mass concentration of aerosol particles which escape and are traced from the SFP under different conditions, respectively. Based on the simulation results, it can be seen that with the increase of particle diameter, DF is going to decrease at first and then increase. There should be a negative correlation between injection velocity and DF. By contrast, there is a positive association between initial water depth and DF. Besides, DFs under vertically downward injection conditions are much lower than that under horizontal injection, due to the appearance of contra-vortex flow adjacent to the free water surface.

Determining the Half Time and Analogy Constants of Radioactive Decay on the Illustration Board of Radioactive Decay with the Capacitor Filling and Discharging Method

Radioactive decay is one of the material to be learned students in the study of physics. However, until now students only learn concepts through existing teaching materials. This is because, the level of danger is very high if students have to deal with radioactive elements. So, it does not allow students to experiment with decay directly. Through an illustration board of radioactive decay, students can learn radioactive decay events by illustrating radioactive decay by capacitor filling and emptying methods. In addition, through this props, students can determine the value of the decay constant and the half-life of a radioactive substance. Based on the results of experiments using capacitors (C) of 4700 μF and resistors (R) of 56 kΩ, the percentage of theoretical experimental data deviation is 2.63% for decay constants, and 3.06% for half-life. This illustrates that there is no significant difference from the theoretical experimental data. So, it can be concluded that the illustration board of radioactive decay is suitable to be used as an illustration tool for radioactive decay events and determine the value of the characteristics of radioactive decay (decay constant and half-life).Keywords: Props, Radioactive Decay, Half-Life, Decay ConstantPeluruhan radioaktif merupakan salah satu materi yang harus dipelajari siswa dalam bidang studi fisika. Namun, sampai saat ini siswa hanya mempelajari konsep melalui bahan ajar yang ada. Hal tersebut dikarenakan, tingkat bahaya yang sangat tinggi jika siswa harus berhadapan dengan unsur radioaktif. Sehingga, tidak memungkinkan siswa melakukan percobaan peluruhan secara langsung. Melalui alat illustration board of radioactive decay, maka siswa dapat mempelajari peristiwa peluruhan radioaktif melalui pengilustrasian peluruhan radioaktif dengan metode pengisian dan pengosongan kapasitor. Selain itu, melalui alat peraga ini siswa dapat menentukan nilai konstanta peluruhan dan waktu paruh dari suatu zat radioaktif. Berdasarkan hasil percobaan dengan menggunakan kapasitor (C) sebesar 4700 μF dan resistor (R) sebesar 56 kΩ, diperoleh persentase penyimpangan data percobaan dengan teoritis sebesar 2,63% untuk konstanta peluruhan, dan 3,06% untuk waktu paruh. Hal tersebut menggambarkan bahwa tidak terdapat perbedaan yang signifikan dari data hasil percobaan dengan teoritis. Sehingga, dapat disimpulkan bahwa alat illustration board of radioactive decay cocok untuk dijadikan alat ilustrasi peristiwa peluruhan radioaktif dan menentukan nilai karakteristik peluruhan radioaktif (konstanta peluruhan dan waktu paruh).Kata kunci: Alat Peraga, Peluruhan Radioaktif, Waktu Paruh, Konstanta Peluruhan

MATHEMATICAL MODELLING OF THE ANALYTICAL AND NUMERICAL SOLUTION OF NON-STATIONARY INITIAL-VALUE PROBLEMS BY MAPLE SOFTWARE.

With the passage of time and the development of technology, humanity is exploring new unknown problems that require complex analytical and numerical mathematical solutions. Due to their complexity differential equations are often used for this purpose. The aim of this work is to solve mathematical models of initial value problems of ordinary differential equations using the analitical method and numerical solution using MAPLE software. Also authors have provided general information about differential equations and diferent ways how they can be solved. As a result have been created two mathematical models which describe process of Determination of the cooling time of a shot animal and decomposition of the radioactive substance. Similar methods are also used to determine the age of objects as well