Zobrazeno 1 - 10
of 57
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:
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
Publikováno v:
Urania, Vol 24, Iss 2 (2018)
DESAIN TERAS REAKTOR TRIGA2000 BANDUNG MENGGUNAKAN TIPE ELEMEN BAKAR MTR U3Si2/Al. Reaktor TRIGA2000 Bandung selama ini menggunakan bahan bakar jenis silinder tetapi bahan bakar tersebut tidak diproduksi lagi. Upaya yang dilakukan agar reaktor TRIGA2
Externí odkaz:
https://doaj.org/article/563e052c42914d5998b89fc81b83dd7d
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
The in-house coupled neutronic and thermal-hydraulic (N/T-H) code of BATAN (National Nuclear Energy Agency of Indonesia), NODAL3, based on the few-group neutron diffusion equation in 3-dimensional geometry using the polynomial nodal method, has been
Externí odkaz:
https://doaj.org/article/32b44cab47ba4a8ca4b2be13bdf68def
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2016 (2016)
This paper reports the results of sensitivity analysis of the multidimension, multigroup neutron diffusion NODAL3 code for the NEACRP 3D LWR core transient benchmarks (PWR). The code input parameters covered in the sensitivity analysis are the radial
Externí odkaz:
https://doaj.org/article/80d610b2de38415785d815fc73b326f4
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2014 (2014)
A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the few-group neutron diffusion equation in 3-dimensional geometry for typical PWR static and transient analyses. The spatial variables are treated by using a polynomial
Externí odkaz:
https://doaj.org/article/0905d46b7d8c402985a5553d9deff768