scholarly journals Implementasi Rencana Kontinjensi Nuklir Reaktor Riset Dalam Upaya Kesiapsiagaan Nuklir

2019 ◽  
Vol 5 (2) ◽  
Author(s):  
Dewi Aprialiani ◽  
I Dewa Ketut Kerta Widana
Keyword(s):  
Nuclear Reactor ◽  
Research Reactor ◽  
Nuclear Research ◽  
Active Role ◽  
Radiation Hazard ◽  
Research Reactors ◽  
Contingency Plan ◽  
Contingency Plans ◽  
Emergency Responses ◽  
Nuclear Emergency

Indonesia has three nuclear research reactors, nemely: RSG-GAS in Serpong, TRIGA2000 reactor in Bandung, and Kartini reactor in Yogyakarta. Besides being useful, nuclear reactor has inharent risk due to its radiation hazard. The research reactor nuclear contingency plan was prepared for nuclear preparedness. The study aimed to analyze the implementation of the research reactors’ nuclear contingency plans. The study used an analytic descriptive qualitative methods. The results showed that the nuclear contingency plans of the three research reactors have different implementation range due to their different hazard risks. However, the nuclear emergency responses were the same, they were: sheltering, evacuation, provision of KI tablets, and prohibition of consumption of local food and contaminated river/ ground water. The research reactors’ nuclear contingency plans have not discussed criteria used for taking nuclear emergency responses. The results also showed that the nuclear contingency plan of RSG-GAS in Serpong and the Kartini reactor in Yogyakarta have been implemented partially. While for the TRIGA2000 reactor nuclear contingency plan in Bandung has not been implemented yet. A legal umbrella is needed to implement the research reactor nuclear contingency plan. Thus, coordination and active role from all stakeholders are needed to be enhanced in order to be able to resolve the existing obstacles and challenges.

State of the Art of Nuclear Reactor Instrument Automation

1974 ◽  
Vol 96 (4) ◽  
pp. 394-398
Author(s):  
M. Taeschner ◽  
R. Gariod
Keyword(s):  
High Performance ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
State Of The Art ◽  
Nuclear Research ◽  
Automation System ◽  
Nuclear Research Reactor ◽  
High Investment

Due to its complexity, nuclear reactor instrument automation is a challenge to engineers. High investment and running costs of a nuclear research reactor imply the use of advanced equipment and concepts for instrument automation when striving for high performance, reliability, and operational convenience under budgetary pressure. The article describes a successfully operating instrument automation system stressing the important underlying concepts trying to avoid too much details on specific hardware which is dependent on the time when one must order things.

Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor

2021 ◽  
Author(s):  
Radojko Jacimovic ◽  
Maria Angela de Barros Correia Menezes
Keyword(s):  
Nuclear Reactor ◽  
Epithermal Neutron ◽  
Research Reactor ◽  
Nuclear Research ◽  
Irradiation Channel ◽  
Spectral Parameters ◽  
K0 Method ◽  
Nuclear Research Reactor ◽  
Research Nuclear Reactor ◽  
The Stability

Abstract The core configuration of the TRIGA MARK I IPR-R1 nuclear research reactor, Brazil, has been modified six times since the first criticality and the neutron fluxes have been determined using experimental and semi theoretical methodologies determining the neutron fluxes in different irradiation channels and devices, applying different procedures and materials. This reactor operates at 100 kW, however, after new configuration for 250 kW in 2001, the carousel no longer rotates during irradiations aiming at preserving the rotation mechanism. In 2003, the spectral parameters were determined experimentally by the "Cd-ratio for multi-monitor" in five specific channels aiming at the application of NAA k0-standardized method. The determinations were repeated applying the same procedure in 2016, 2018 and 2019. Values for thermal and epithermal neutron fluxes as well as f and a spectral parameters were determined. The experimental results for CRM BCR-320R were calculated by the k0-method of NAA, using the spectral parameters for irradiation channel IC-7 obtained in 2003, 2016, 2018 and 2019 and evaluated by En-score. The values showed that the differences in the results compared to those in 2003 were lower than 2.5%, inside the uncertainty of the method. It shows that the k0-method installed in CDTN is reliable and useful for various purposes. The results of the spectral parameter f presented small differences, in a period of 16 years, pointing out the stability of operation of the reactor TRIGA MARK I IPR-R1.

scholarly journals Search for neutron-hidden neutron interbrane transitions with MURMUR, a low-noise neutron passing-through-walls experiment

2019 ◽  
Vol 219 ◽  
pp. 07004
Author(s):  
Coraline Stasser ◽  
Michaél Sarrazin ◽  
Guy Terwagne
Keyword(s):  
Cross Section ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
Nuclear Research ◽  
Elastic Cross Section ◽  
Low Noise ◽  
Beyond The Standard Model ◽  
Important Concern ◽  
The Standard Model ◽  
Nuclear Research Reactor

Multi-braneworld universe is at the heart of many scenarios of physics beyond the Standard Model and the cosmological model ΛCDM. It is thus an important concern to constrain these scenarios which also allow for experiments below the GeV scale. MURMUR is a new neutron passing-through-walls experiment designed to constrain neutron-hidden neutron transitions in the context of braneworlds scenarios. As our visible universe could be a 3-brane embedded in a multidimensional bulk, adjacent hidden 3-branes are often expected. Their existence can be constrained as matter exchange between braneworlds must occur with a swapping probability p. A neutron n can convert into a hidden neutron n′ when scattered by a nucleus with cross section σ(n → n′) ∝ σE(n → n)p, where σE is the usual elastic cross-section. Hidden neutrons could therefore be generated in the moderator medium of a nuclear reactor, where high-flux neutrons undergo many elastic collisions. All the theoretical and technological keys of this experiment soon to be installed at the nuclear research reactor BR2 (SCK.CEN, Mol, Belgium) are introduced.

scholarly journals Thermal-hydraulically calculation for the Dalat nuclear research reactor

1991 ◽  
Vol 13 (4) ◽  
pp. 14-19
Author(s):  
Ngo Phu Khang
Keyword(s):  
Nuclear Reactor ◽  
Research Reactor ◽  
Nuclear Research ◽  
Core Domain ◽  
The Core ◽  
Nuclear Research Reactor

This paper concerns with thermal-hydraulically calculation for the core domain of the Dalat nuclear reactor in the nominal regime of works. On the base of this calculation some conclusions. On thermal safely of the reactor are conducted.

Anthropogenic Releases of Radiocarbon and its Concentration Burden in Environment

2020 ◽  
Vol 10 (1) ◽  
pp. 23-32
Author(s):  
Abdul Ghaffar ◽  
Zainab Hafeez ◽  
Syeda Maria Ali
Keyword(s):  
Wind Direction ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
Climatic Factors ◽  
Nuclear Research ◽  
Prevailing Wind ◽  
Prevailing Wind Direction ◽  
Pee Dee ◽  
Nuclear Research Reactor ◽  
Vegetation Samples

: The radiocarbon (14C) concentrations in air and vegetation samples around a nuclear research reactor were studied. Objective: 14C concentrations in the air and vegetation samples around the nuclear research reactor were measured to assess its 14C burden on the environment. Methods: Air samples were collected by converting CO2 into Na2CO3 by using a specified system. Leaf samples were carbonized to convert organic carbon into inorganic carbonates. The samples were converted into carbamate through carbosorb systems with 74% efficiency. The fractionation of 14C for each sample was corrected and normalized to a 13C composition of -25‰ Pee Dee Belemnite. Results: 14C concentrations in the air and vegetation samples around the nuclear research reactor were found to range from 158 to 406 Bq/Kg and 162 to 339 Bq/kgC, respectively. The highest concentrations of 14C were found in the samples close to the reactor and along the prevailing wind direction. The specific activities of the samples decreased with an increase in the distance from the reactor and in the opposite to prevailing wind direction. In addition to the distance from the reactor and wind direction, the local Suess effect was an additional factor affecting the 14C activities in the air and vegetation samples. Conclusion: One can conclude that other than the 14C emissions from the nuclear reactor, local Suess effects and climatic factors (wind directions) dilute and disperse 14C concentrations in the atmosphere and consequently decrease its availability for uptake and accumulation by plants at 4-5 km aerial distance from the point of release in prevailing wind direction.

scholarly journals Production of Radioisotopes and Radiopharmaceuticals at the Dalat Nuclear Research Reactor

2014 ◽  
Vol 4 (1) ◽  
pp. 46-56
Author(s):  
Van Dong Duong ◽  
Ngoc Dien Pham ◽  
Van Cuong Bui ◽  
Phuoc Tho Mai ◽  
Thi Thu Nguyen ◽  
...  
Keyword(s):  
Quality Control ◽  
Production Rate ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
Operation Time ◽  
Nuclear Research ◽  
Radioisotope Production ◽  
Production Lines ◽  
Nuclear Research Reactor ◽  
Production Programme

After reconstruction, the Dalat Nuclear Research Reactor (DNRR) was inaugurated on March 20th, 1984 with the nominal power of 500 kW. Since then the production of radioisotopes and labelled compounds for medical use was started. Up to now, DNRR is still the unique one in Vietnam. The reactor has been operated safely and effectively with the total of about 37,800 hrs (approximately 1,300 hours per year). More than 90% of its operation time and over 80% of its irradiation capacity have been exploited for research and production of radioisotopes. This paper gives an outline of the radioisotope production programme using the DNRR. The production laboratory and facilities including the nuclear reactor with its irradiation positions and characteristics, hot cells, production lines and equipment for the production of Kits for labelling with 99mTc and for quality control, as well as the production rate are mentioned. The methods used for production of 131I, 99mTc, 51Cr, 32P, etc. and the procedures for preparation of radiopharmaceuticals are described briefly. Status of utilization of domestic radioisotopes and radiopharmaceuticals in Vietnam is also reported.

scholarly journals Changes of the Neutron Flux of the Nuclear Reactor Triga Mark III Since the Conversion from High to Low 235U Enrichment

2021 ◽  
Vol 8 (2) ◽  
pp. 149-153
Author(s):  
C. Vázquez-López ◽  
O. Del Ángel-Gómez ◽  
R. Raya-Arredondo ◽  
S. S. Cruz-Galindo ◽  
J. I. Golzarri-Moreno ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Nuclear Reactor ◽  
Research Reactor ◽  
Nuclear Research ◽  
Reactor Power ◽  
Uranium Fuel ◽  
Acrylic Sheet ◽  
Enriched Uranium ◽  
Reactor Operating ◽  
Fuel Elements

The neutron flux of the Triga Mark III research reactor was studied using nuclear track detectors. The facility of the National Institute for Nuclear Research (ININ), operates with a new core load of 85 LEU 30/20 (Low Enriched Uranium) fuel elements. The reactor provides a neutron flux around 2 × 1012 n cm-2s-1 at the irradiation channel. In this channel, CR-39 (allyl diglycol policarbonate) Landauer® detectors were exposed to neutrons; the detectors were covered with a 3 mm acrylic sheet for (n, p) reaction. Results show a linear response between the reactor power in the range 0.1 - 7 kW, and the average nuclear track density with data reproducibility and relatively low uncertainty (±5%). The method is a simple technique, fast and reliable procedure to monitor the research reactor operating power levels.

scholarly journals Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor

Nukleonika ◽  
2017 ◽  
Vol 62 (1) ◽  
pp. 37-45 ◽  
Author(s):  
Zohreh Gholamzadeh ◽  
Seyed Mohammad Mirvakili ◽  
Amin Davari ◽  
Mosoumeh Alizadeh ◽  
Atieh Joz-Vaziri
Keyword(s):  
Research Reactor ◽  
Geometry Optimization ◽  
Nuclear Research ◽  
Computational Results ◽  
Temperature Peak ◽  
Potential Production ◽  
Research Reactors ◽  
Liquid Samples ◽  
Hydraulic Conditions ◽  
Nuclear Research Reactor

Abstract The activation method for 99Mo production in comparison to fissionable target irradiation in research reactors is less preferable. Therefore, 99Mo yield using UO2SO4 samples was theoretically investigated. Computational results revealed admirable potential of the liquid samples for 99Mo production. Low-concentrated uranyl sulphate samples could easily be handled by the irradiation box. The sample geometry optimization improves thermal hydraulic conditions and production yield. The optimized geometry including only 0.12 g 235U produced 57Ci99Mo at end-of-irradiation (EOI) with a temperature peak of 72°C during the irradiation.

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

2020 ◽  
Vol 6 (2) ◽  
Author(s):  
Damian E. Ramajo ◽  
Santiago F. Corzo ◽  
Norberto M. Nigro
Keyword(s):  
Fluid Dynamics ◽  
Research Reactor ◽  
Water System ◽  
Nuclear Research ◽  
Main Line ◽  
Research Reactors ◽  
Open Type ◽  
Pressure Fields ◽  
Nuclear Research Reactor ◽  
Computational Fluid Dynamics Cfd

Abstract The Pohang University of Science and Technology facility (POSTECH) experiments to mimic the siphon breaker system (SBS) of an open-type nuclear research reactor were simulated by computational fluid dynamics (CFD). Two siphon breaker lines (SBL) and one siphon breaker hole (SBH) designs were solved with the open field operation and manipulation code (openfoam). The air–water system was solved using the volume of fluid (VOF) method, and the turbulence was modeled by means of the standard k–ϵ model. The pool drainage by siphonage was captured and the siphon break phenomena due to the entrance of air through the SBS were captured. The velocity and pressure fields in the main line were analyzed in depth. The pool undershooting height (hun) as well as the flow rate through the main line were quite well estimated without the need of introduce any fitting parameter in the computational model.

scholarly journals Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor

2019 ◽  
Vol 7 (2B) ◽  
Author(s):  
Aldo Márcio Fonseca Lage ◽  
Adriano Almeida Massaud Felippe ◽  
Amir Zacarias Mesquita
Keyword(s):  
Nuclear Reactor ◽  
Nuclear Research ◽  
Reactor Power ◽  
Modern Concept ◽  
Video Monitor ◽  
Operational Parameters ◽  
Computational System ◽  
Research Reactors ◽  
Reliable Monitoring ◽  
Implementation Stages

The instrumentation of nuclear reactors is designed based on the reliability, redundancy and diversification of control systems. The monitoring of the parameters is of crucial importance with regard to the operational efficiency and safety of the installation. Since the first criticality of a nuclear reactor, achieved by Fermi et al. in 1942, there has been concern about the reliable monitoring of the parameters involved in the chain reaction. This paper presents the current stage of the system of simulation, which is under development at the CDTN, which intends to simulate the operation of the Triga IPR-R1 nuclear reactor, involving the evolution of neutron flux and reactor power related events. The system will be developed using LabVIEW® software, using the modern concept of virtual instruments (VIs) that are visualized in a video monitor. For the implementation of this model, computational tools and systems analysis are necessary, which help and facilitate the implementation of the simulator. In this article we will show some of these techniques and the initial design of the model to be implemented. The design of a computational system is of great importance, since it guides in the implementation stages and generates the documentation for later maintenance and updating of the computational system. It is noteworthy that the innovations developed in research reactors are normally used in power reactors. The relatively low costs enable research reactors to be an excellent laboratory for developing techniques for future reactors.

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