Alexander Agung

Universitas Gadjah Mada | UGM · Department of Nuclear Engineering and Engineering Physics

From a safety point of view, the fuel-cladding of the current design of the KLT-40S reactor still carries a potential risk in the event of a loss-of-coolant accident (LOCA) allowing the formation of hydrogen gas. The concept of accident tolerant fuels (ATF) offers a variety of new safer fuel-cladding materials, one of which is U3Si2-FeCrAl, a poten...

Due to an increase in global nuclear security issues, there need to be improvements in human resources and security measures. The Republic of Indonesia is an archipelago country, which makes surveilling for nuclear security threats complicated. Recent radioactive material smuggling incidents proved that Indonesian police and security officers’ know...

Fuel loading pattern optimization is a complex problem because there are so many possibilities for combinatorial solutions, and it will take time to try it one by one. Therefore, the Polar Bear Optimization Algorithm was applied to find an optimum PWR loading pattern based on BEAVRS. The desired new fuel loading pattern is the one that has the mini...

Cancer is a disease that leading cause of death worldwide. In 2012, there were 8.2 million deaths caused by cancer. Cancer suffered by patients can metastasize to other body parts, such as the lungs, liver, brain, and bones. The risk of bone metastases becomes higher after cancer has spread to other body tissues, so it is necessary to do more speci...

KLT-40S nuclear reactor is a small modular floating nuclear power plant made by Russia as a conventional light water reactor (LWR) problem solution nowadays, such as high overnight cost, long commissioning period, and lack of flexibility in supplying a small load of electricity and supplying electricity to isolated areas. With those characteristics...

One of Floating Nuclear Power Plant (FNPP) designs in the world is currently being built by Russian Federation, named “Academic Lomonosov,” which uses two PWR types, KLT-40S as its power unit. However, too little information regarding its detailed technical specification is available, including its thermal-hydraulics parameters. The objective of th...

KLT-40S has an advantage as a floating nuclear power plant with high mobility and portability because it can be towed throughout the sea to the destination. The changes in the sea conditions when the nuclear reactor operates should be accounted for the thermal-hydraulic analysis. The sea state condition and the reactor power were varied to know how...

NuScale is an integral UO2 fueled PWR that operates with natural circulation. In this study thermal-hydraulic analysis was carried out on the NuScale primary system to observe the natural convection phenomenon when the fuel was changed to mixed oxide (MOX). The use of MOX could increase the neutron advantage, but it was offset by enlargement of the...

TerraPower Traveling Wave Reactor-Prototype (TWR-P) provides the potential to properly address depleted uranium waste problems through an improved uranium utilization system. Despite all the economic and environmental benefits, the concept is shrouded with criticism against its use of sodium as the coolant due to the experience of sodium leaks and...

Space exploration is very important for the future of the earth and human beings as it may eliminate earth overpopulation and overcome diminishing of earth resources. One of the obstacles of the space exploration mission is the energy source for the spacecraft. One alternative is using a nuclear reactor as an energy source in spacecraft. A conceptu...

National Atomic Energy Agency of Indonesia (BATAN) has considered the High Temperature Gas-cooled Reactor (HTGR) for energy fulfillment solution in Indonesia. HTGR is a high-level safety Gen. IV power reactor, no melting core when an accident occurs, which very suitable for Indonesia. Indonesian HTGR development is initiated by the development of i...

Reduced-moderation pressurized water reactor (RMPWR) utilised thorium (Th) as the fuel in exchange for uranium (U) due to its huge advantages in term of neutronics characteristics, including low void and moderator temperature coefficient, and the potential of breeding into fissile fuel 233 U. In RMPWR, the water to fuel ratio is reduced to 50% of t...

The Kartini Triga Mark II Research Reactor (Kartini TM2RR), one of the three research reactors in Indonesia, is a pool-type reactor with a thermal power of 100 kW that has been operating since 1979 and has legal operation licensing until 2019 from the regulatory body. As of 2018, the reactor is composed of 71 cylindrical fuel elements of height 66...

One of proposed Accident Tolerant Fuel (ATF) concept is Fully ceramic micro-encapsulated fuel (FCMF). FCMF using uranium mononitride (UN) has better safety aspects than UO2 pellet fuel although it might not have a better neutronic performance due to the presence of matrix and high neutron-induced interaction of 14N. Before implementing UN-FCMF tech...

Integral PWR using MOX fuel can be used as solution to handle electrification problem in archipelagic nations as well as to accomodate the transition of fuel from UO2 to MOX. Integral PWR is a modular nuclear power plant with 160 MWt for each module. Recently, Integral PWR use UO2 fuel as the main fuel. This research’s purpose is to determine the c...

Safety analysis of a PWR fuelled with ATF (Accident-Tolerant Fuel) has been performed at LB-LOCA condition. The ATF being used is uranium silicide (U3Si2) and FCMF (Fully Ceramic Microencapsulated Fuel) with silicon carbide (SiC) and FeCrAl alloy as a cladding material. The objective of this research is to obtain dynamic characteristics of ATF-fuel...

The Kartini reactor has been operating almost 40 years. New extension of license in 2019 requires in-depth analysis of the safety requirements set by Bapeten. The latest regulation of the regulatory body of 2014 requires computational validation for core safety parameters. In this research, TRIGA MCNP software has been used for Kartini reactor as c...

Nuclear fuel management was done by optimizing fuel loading pattern in a reactor core. Practically, performing fuel loading pattern optimization was difficult because of its combinatorial problem complexity which needed to be solved. Therefore, Quantum-inspired Evolutionary Algorithm (QEA) which could solve the combinatorial problem faster than con...

A study about Resource Renewable Boiling Water Reactor (RBWR) core, a reduced moderation boiling water reactor that features the breeding ratio larger than 1 was conducted. This study focuses on the neutronic performances of the core and aims to investigate the core sustainability when using thorium as the main fertile fuel. A fuel-self-sustaining...

High Temperature Reactor (HTR) merupakan reaktor yang dapat beroperasi dengan suhu yang tinggi sehingga dapat mendukung aplikasi panas proses industri lain. Konsep reaktor ini menghasilkan energi yang berkelanjutan, menawarkan peningkatan resistensi proliferasi nuklir, menjanjikan operasi dengan burnup yang tinggi, dan potensi kegagalan bahan bakar...

Salah satu komponen penting dalam pembangkitan daya pada reaktor nuklir adalah steam generator. High Temperature Gas-Cooled Nuclear Reactor (HTGR) merupakan salah satu reaktor nuklir dengan suhu keluaran yang tinggi serta menggunakan steam generator berjenis once through helical coil. Salah satu potensi kecelakaan dasar desain pada HTGR adalah Depr...

Diktat ini berisikan materi kuliah Analisis Reaktor Nuklir yang diberikan pada Program Studi Sarjana Teknik Nuklir, Universitas Gadjah Mada, Yogyakarta.

Laporan teknis kerjasama Swakelola BAPETEN

Laporan teknis kegiatan kerjasama swakelola BAPETEN

Laporan teknis kegiatan kerjasama swakelola BAPETEN

Simulation using Monte Carlo code has been conducted to determine the distribution of absorbed dose to the breast brachytherapy with ¹³¹Cs and ¹⁰³Pd radionuclide sources. Simulations performed on stage I breast cancer with cancer diameter is 2 cm. Sources of radionuclides simulated in the form of seed is modeled with CS-1 whic...

Laporan ini membahas tentang (i) latar belakang adanya PLTN Terapung dan lingkup kajian, (ii) kajian desain PLTN Terapung, (iii) pertimbangan pemilihan tapak, (iv) analisis keselamatan terkait desain PLTN terapung, (v) dampak PLTN Terapung terhadap lingkungan dan penduduk, (vi) aspek keamanan dan safeguard, (vii) aspek legal dan (viii) kesimpulan d...

ABSTRAK HTR-PM adalah reaktor generasi IV milik Tiongkok yang akan beroperasi dan tersambung ke grid pada akhir tahun 2017. HTR-PM menggunakan dua modul teras dengan daya termal masing-masing modul 250 MWt dan mampu menghasilkan daya elektrik sebesar 210 MWe. Pada penelitian kali ini daya termal HTR-PM diubah menjadi 150 MWt. Studi awal optimasi b...

Neutronic calculations have been performed to a fluidized bed nuclear reactor that uses advanced coated particles to improve its endurance against irradiation and high temperature. The calculation is intended to determine whether reactor characteristics have been significantly compromised. The characteristic of the reactor is assessed by investigat...

Neutronic calculations have been performed to a fluidized bed nuclear reactor which uses advanced coated particles to improve its endurance against irradiation and high tem- perature. The calculation is intended to determine whether reactor characteristics has been significantly compromised. The characteristic of the reactor is assessed in this res...

ABSTRACT This paper gives an account of the development and validation of an up-to-date coupled neutronic/thermal-hydraulic model for the Swedish Forsmark boiling water reactor. The model will be used for analyses of the consequences of the planned power uprate from 2928 MWth to 3253 MWth. At first, the development of the PARCS and RELAP5 models a...

This Technical Report gives an account on the validation of an up-to-date coupled PARCS/RELAP5 model for the Forsmark 2 at 120% uprated power. At first the operation test PI 661 is touched upon and then the development of the models are described. On the neutronic side, cross-sections data was generated, allowing feeding PARCS with realistic data....

This article gives an account of the development and validation of the PARCS/RELAP5 model of the Ringhals-3 unit against a load rejection transient, which occurred on November 28, 2010. The third unit of the Ringhals nuclear power plant comprises a 3-loop Westinghouse design pressurized water reactor on the Swedish West Coast. At first, the develo...

Research within nuclear safety and radiation protection is necessary in order to maintain the high level of competence required by an expert authority. In the field of reactor safety research, SSM's goals are to support regulation and contribute to national competence in the area of nuclear safety. A technical support organization on deterministic...

Since the large number of possible combination for the fuel assembly loading in the core at the beginning of reactor operation, the core configuration optimized to find an optimal core configuration that will achieve maximum k eff at end of cycle and minimum power peaking factor (PPF). This optimization has 2 Genetic Algorithm methods, the first me...

Optimizing loading/reloading pattern design is one of nuclear fuel management activities in order to reduce fuel cycle costs while satisfying safety constraints and operational targets. Multiplication factor at the end of cycle and maximum power peaking factors are the parameters to define the optimal LP design. This optimization initial fuel loadi...

Since there are large numbers of possible combinations for the fuel assembly loading in the core at the beginning of reactor operation, the core configuration needs to be optimized. Optimized conition was defined as core which achieves maximum k eff at end of cycle and minimum power peaking factor (PPF). This optimization had been done in 2 methods...

Aktivitas produksi pabrik kelapa sawit (PKS) menghasilkan limbah dalam volume sangat besar. Limbah yang dihasilkan dapat berupa padatan maupun cair. Limbah tersebut memiliki nilai kalor cukup tinggi. Pemanfaatannya akan menghasilkan bahan bakar yang bisa dipakai salah satunya untuk pembangkitan listrik. Untuk sebuah PKS dengan kapasitas 100 ribu t...

At this research, a schema of coupled system between Molten Salt Reactor and the electrolysis plant for hydrogen production at the rate of 5 kg/s have been done successfully. Electrical and heat energy for electrolysis process are supplied by MSR. The effect of variation of current density which enter the cells of electrolyzer to perform electrolys...

A new design of a fluidized bed has been proposed and it has been shown that under steady condition the reactor is able to produce power up to 120 MW. To study the behavior of the reactor under transient conditions as well as its stability, a model describing the coupling of neutronics, thermal hydraulics, and fluidization is applied. The objective...

Analysis in feasibility study, basic design, and detail engineering design in many hydro powerplant in Indonesia is currently still conducted by applying separate computation module. A simple but integrated design module capable in conducting analysis of technical, economical, and financial feasibility is therefore needed. This research developed...

A preliminary investigation about neutronic performance of online refueling Passive Compact Molten Salt Reactor (PCMSR) 7 LiF-ThF 4 -PuF 4 (Th 232 -Pu 239 -Pu 240 -Pu 241 -Pu 242) fueled and 7 LiF-BeF 2 (secondary salt) coolant has been accomplished. This analysis was done by solving the depletion equation of fuel extraction system by DVODE solver...

A coolant flow transient analysis of Small Simple and Safe Reactor (SSSR) primary coolant loop without any postulated accidents has been performed. The simulation was performed by using Simulink. The reactor uses the integral concept where core and heat exchanger are located in a vessel. Analysis was conducted by quasi-static approximation of coupl...

Character education may give a social assistance in such a way that an individual can grow to appreciate his freedom in living together with other people in this world. The character education of human resources in nuclear technology should address a two-fold objective, i.e. satisfying the international demand without compromising the national one....

Produksi hidrogen dalam skala besar dapat dilakukan dengan sistem "High Temperature Electrolysis (HTE)". Reaktor nuklir generasi IV, terutama Molten Salt Reactor (MSR), mampu menghasilkan temperatur tinggi. Pengoptimalan produksi hidrogen dapat dilakukan dengan sistem kopel antara kedua instalasi ini. Kenaikan temperatur salt dari MSR sangat mempen...

In this thesis a conceptual design of an innovative high temperature reactor based on the fluidization principle (FLUBER) is proposed. The reactor should satisfy the following requirements: (a) modular and low power, (b)) large shutdown margin, (c) able to produce power when the bed of particles expands and stop as soon as the coolant flow is lost,...

Modeling of the space-dependent dynamics of a fluidized bed nuclear reactors has been performed. The model consists of coupled neutronics, heat transfer as well as fluid dynamics/fluidization. The granular kinetic theory is also incorporated to model the phenomena of gas-solid interaction. A computational scheme for the neutronics comprises the eve...

A preliminary study on the neutronics of Fixed Bed Nuclear Reactor (FBNR) has been performed by using the SRAC code. Uranium dioxide is used as fuel in pebble form (i.e. Micro Fuel Elements), in which coated particles are embedded. The analysis was performed on a clean core without control rods nor burnable poisons. The objective of the study is to...

The collimator design to provide neutron radiography from neutron generator source has been done. Collimator is used to gain optimum thermal neutron flux with radiation contaminant (epitermal neutron and gamma) as low as possible. The design process was done by simulation using Monte Carlo N-Particle (MCNP) Code. The results are tallies that indica...

Modeling of the space-dependent dynamics of FLUBER has been performed. The model consists of coupled neutronics, heat transfer as well as fluid dynamics/fluidization. A computational scheme for the neutronics comprises a second order even-parity finite element method for solving the Boltzman transport equation, while for the the fluid dynamics a no...

The use of supercritical water on a reactor core design makes the the reactor design simpler, smaller and more efficient. Based on this assumption, a nuclear reactor system will be designed. The reactor design is a modification of PWR design which has thermal power 300 MWth and incorporates an integrated primary system in a single pressure vessel....

A preliminary study about Molten Salt Fast Breeder Reactor with 7LiF- ThF4-PuF4 (Th232-Pu239-Pu240-Pu241-Pu242) fuel and 7LiF-BeF2 (secondary salt) coolant has been performed. This study is done by using SRAC2003 computer code. This study focuses on core reactivity coefficient (fuel temperature and void), and void reactivity coefficient of coolant...

This paper describes several modifications to the design of a fluidized bed nuclear reactor in order to improve its performance. The goal of these modifications is to achieve a higher power output, requiring an excess reactivity of 4% at maximum expansion of the bed. The modifications are also intended to obtain a larger safety margin when the reac...

Numerical simulations have been performed to investigate the possibility of passive decay heat removal in a fluidized bed nuclear reactor. The conduction, convection and radiative heat transfer were included and the high Reynolds number k-ε turbulence model was applied for the flow calculations. The P 1 and S N approximation methods for participati...

Numerical simulations have been performed to investigate the possibility of passive decay heat removal in a fluidized bed nuclear reactor. The conduction, convection and radiative heat transfer were included and the high Reynolds number k-ε turbulence model was applied for the flow calculations. A P 1 approximation method for participating media wa...

A theoretical model describing the coupling of neutronics, thermohydraulics and fluidization in a fluidized bed nuclear reactor is presented. The stability of the system is investigated by linearizing and perturbing the system around its equilibrium points and identifying the root loci of the sytem. It is found that within the operational range, th...

FLUBER (Fluidized Bed Thermal Fission Nuclear Reactor) is a conceptual design of a modular reactorutilizing the concept of fuel pellet suspension. It consists of TRISO coated fuel particles contained in agraphite-walled cylinder. Helium is used as a coolant and as fluidizing medium.It has been observed experimentally that particles in a gas-solid f...

An investigation to the steam generating plant in Madukismo sugar cane factor has been performed to determine the cost of products. This activity was carried out by collecting field data of sugar cane factory and the data was used as operation parameter data of initial configuration. Further investigation was performed for several proposed configur...

A theoretical model describing the coupling of neutronics, thermohydraulics and fluidization in a fluidized bed nuclear reactor is presented. Simulations of operational transient conditions are performed, viz. a decrease of coolant flow rate and a change of coolant inlet temperature. These simulations show that the fuel temperature remains below th...