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Equilibrium Core Design of Reaktor Daya Eksperimental

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22076

2019

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Preliminary Analysis on Burnup Calculation of Several Arrangement of TRISO and Pebble inside an MCNP Model of HTR Core

Journal of physics. Conference series, 2021-11, Vol.2072 (1), p.12008

2021

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Study on Control Rod Reactivity of Small Pebble Bed Reactor with Wallpaper Fuel Design

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12021

2021

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Pebble Bed High Temperature Reactor for Electric and Cogeneration Application

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12032

2021

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Study on MOX Core Characteristics of Experimental Power Reactor using MCNP6 Code

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22031

2019

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Impact of Different Nuclear Data Library on Control Rod Reactivity Worth Calculation of Small Pebble Bed Reactor

Journal of physics. Conference series, 2021-10, Vol.2048 (1), p.12029

2021

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The development of TRIAC-BATAN: a triso fuel performance analysis code

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22035

2019

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Burnup Calculation Study of Pebble Bed Equilibrium Core

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22036

2019

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Criticality Study on Different Pebble Arrangement inside HTR Reactor Core

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12038

2021

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Analysis of water ingress accident in the RDE core using MCNPX

Journal of physics. Conference series, 2021-02, Vol.1772 (1), p.12044

2021

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The Challenges of Implementing the Indonesian Experimental Power Reactor (RDE) Program

Journal of physics. Conference series, 2021-10, Vol.2048 (1), p.12001

2021

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Optimization of PeLUIt-150 Conceptual Design

Journal of physics. Conference series, 2021-10, Vol.2048 (1), p.12027

2021

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Physical protection system effectiveness calculation in nuclear reactor facility using EASI code: case study sabotage scenario

Journal of physics. Conference series, 2021-11, Vol.2072 (1), p.12010

2021

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Criticality and Burnup Study on Different TRISO Modelling of HTR Pebble

Journal of physics. Conference series, 2019-04, Vol.1198 (2), p.22078

2019

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RDE Design Strategy for Indonesia Experimental NPP

Journal of physics. Conference series, 2021, Vol.2048 (1)

2021

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Study on Characteristic of Temperature Coefficient of Reactivity for Plutonium Core of Pebbled Bed Reactor

Journal of physics. Conference series, 2018-02, Vol.962 (1), p.12058

2018

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High-resolution probabilistic seismic hazard analysis of West Nusa Tenggara, Indonesia

Journal of seismology, 2021-06, Vol.25 (3), p.937-948

2021

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Power Peaking Effect of OTTO Fuel Scheme Pebble Bed Reactor

Journal of physics. Conference series, 2018-02, Vol.962 (1), p.12065

2018

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Safety assessment of pressure vessel components for Reaktor Daya Eksperimental

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12023

2020

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Preliminary Neutronic Design of High Burnup OTTO Cycle Pebble Bed Reactor

Atom Indonesia, 2015-04, Vol.41 (1), p.7-15

2015

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Preliminary Study on Mass Flow Rate in Passive Cooling Experimental Simulation During Transient Using NC-Queen Apparatus

Atom Indonesia, 2014-12, Vol.40 (3), p.141-147

2014

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Investigation on neutronic properties of ZrC coated advanced TRISO fuel for high-temperature gas-cooled reactors

Journal of physics. Conference series, 2020-01, Vol.1436 (1), p.12036

2020

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The development of EASI-based multi-path analysis code for nuclear security system with variability extension

Nuclear engineering and technology, 2022, Vol.54 (10), p.3604-3613

2022

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The development of EASI-based multi-path analysis code for nuclear security system with variability extension

Nuclear Engineering and Technology, 2022, 54(10), , pp.3604-3613

2022

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Estimation on Pressure and Velocity Parameter in the Fuel Handling Pneumatic Design of RDE

Journal of physics. Conference series, 2020-03, Vol.1493 (1), p.12002

2020

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Equilibrium Core Design of Reaktor Daya Eksperimental

Preliminary Analysis on Burnup Calculation of Several Arrangement of TRISO and Pebble inside an MCNP Model of HTR Core

Study on Control Rod Reactivity of Small Pebble Bed Reactor with Wallpaper Fuel Design

Pebble Bed High Temperature Reactor for Electric and Cogeneration Application

Study on MOX Core Characteristics of Experimental Power Reactor using MCNP6 Code

Impact of Different Nuclear Data Library on Control Rod Reactivity Worth Calculation of Small Pebble Bed Reactor

The development of TRIAC-BATAN: a triso fuel performance analysis code

Burnup Calculation Study of Pebble Bed Equilibrium Core

Criticality Study on Different Pebble Arrangement inside HTR Reactor Core

Analysis of water ingress accident in the RDE core using MCNPX

The Challenges of Implementing the Indonesian Experimental Power Reactor (RDE) Program

Optimization of PeLUIt-150 Conceptual Design

Physical protection system effectiveness calculation in nuclear reactor facility using EASI code: case study sabotage scenario

Criticality and Burnup Study on Different TRISO Modelling of HTR Pebble

RDE Design Strategy for Indonesia Experimental NPP

Study on Characteristic of Temperature Coefficient of Reactivity for Plutonium Core of Pebbled Bed Reactor

High-resolution probabilistic seismic hazard analysis of West Nusa Tenggara, Indonesia

Power Peaking Effect of OTTO Fuel Scheme Pebble Bed Reactor

Safety assessment of pressure vessel components for Reaktor Daya Eksperimental

Preliminary Neutronic Design of High Burnup OTTO Cycle Pebble Bed Reactor

Preliminary Study on Mass Flow Rate in Passive Cooling Experimental Simulation During Transient Using NC-Queen Apparatus

Investigation on neutronic properties of ZrC coated advanced TRISO fuel for high-temperature gas-cooled reactors

The development of EASI-based multi-path analysis code for nuclear security system with variability extension

The development of EASI-based multi-path analysis code for nuclear security system with variability extension

Estimation on Pressure and Velocity Parameter in the Fuel Handling Pneumatic Design of RDE

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