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RISPressurized Water Reactor Mixed Oxide/UO2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper presents static and transient solutions for the pressurized water reactor (PWR) MOX/UO2 transient benchmark by Serpent 2 Monte Carlo (MC) code and open nodal core simulator called Abu Dhabi Polytechnic Reactor ...
Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A new design of a small power accelerator-driven system (ADS) using inert matrix fuel—ceramic–ceramic matrix (CERCER) and ceramic-metallic matrix (CERMET) was proposed in our previous work for high transmutation rate, small ...
Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper presents the generation and the verification of the few-group homogenized cross section for Batan-FUEL code. This code is routinely used for fuel management in the G. A. Siwabessy Multipurpose Reactor (RSG-GAS). ...