Zobrazeno 1 - 10
of 75
pro vyhledávání: '"Surian Pinem"'
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 5, Pp 1775-1782 (2023)
Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Le
Externí odkaz:
https://doaj.org/article/a2797f97663f48a4aec1ed4291f0d376
Autor:
Wahid Luthfi, Surian Pinem
Publikováno v:
Acta Polytechnica, Vol 63, Iss 4 (2023)
This paper describes the effect of cross-section data generated by several codes on calculated neutronic parameters. The Pressurized Water Reactor Mixed Oxide and Uranium Oxide (PWR MOX/UO2) Core Transient Benchmark case was chosen because it has bee
Externí odkaz:
https://doaj.org/article/9711435a26d9494cbbbc515edfabcca6
Publikováno v:
Acta Polytechnica, Vol 62, Iss 4, Pp 438-444 (2022)
A nuclear reactor cooling system that has been operating for a long time can carry some debris into a fuel coolant channel, which can result in a blockage. An in-depth two-dimensional simulation of partial channel blockage can be carried out using FL
Externí odkaz:
https://doaj.org/article/74b89e355d6f4be2864c255e7c323a01
Autor:
Wahid Luthfi, Surian Pinem
Publikováno v:
Urania, Vol 27, Iss 1, Pp 47-56 (2021)
VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK. Determination of neutronic parameter value is an important part in determining reactor safety, so accurate calculation results can be obtained. Thi
Externí odkaz:
https://doaj.org/article/742b5804deb24738a75ba6628f8d58b9
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2022 (2022)
Steady-state and transient analysis of reactor core under Reactivity-Initiated Accident (RIA) conditions are important for reactor operation safety. The reactor dynamics are influenced by neutronic and thermal-hydraulic aspects of the core. In this s
Externí odkaz:
https://doaj.org/article/700d9405fef5453681e717f90bd5b356
Publikováno v:
Nuclear Engineering and Technology. 55:1775-1782
Publikováno v:
Jurnal Teknologi. 84:191-199
Due to several characteristics, such as geometry, compact core, high coolant flow, and high neutron flux, the burn-up study of the RSG-GAS multi-purpose reactor provides challenges when employing a neutronic calculation. For the burn-up analysis, two
Publikováno v:
Urania, Vol 25, Iss 3 (2019)
NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR. Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation. Dur
Externí odkaz:
https://doaj.org/article/8452323f43e0464086c7dbd9ed788fb9
Reaktor nuklir merupakan fasilitas atau instalasi yang menghasilkan energi panas dan radiasi yang bekerja berdasarkan reaksi fisi atau reaksi pembelahan dari inti bahan bakar nuklir. Reaktor nuklir dapat dimanfaatkan energi panasnya, baik untuk listr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f8b29c5e0875145c1e56d7263e3702d4
https://doi.org/10.55981/brin.584
https://doi.org/10.55981/brin.584
Publikováno v:
Science and Technology Applications.
The current work investigates the impact of MOX fuel introduction on AP1000 neutronic characteristics. The MCNP code with new silicon carbide cladding and the AP1000 core with three 235U enrichment zones (2.35%, 3.40%, and 4.45%) were used to perform