Zobrazeno 1 - 10
of 109
pro vyhledávání: '"Peng Hong Liem"'
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:
Donny Hartanto, Peng Hong Liem
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 12, Pp 2725-2732 (2020)
This paper presents the neutronics benchmark analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS (Reaktor Serba Guna G.A. Siwabessy) calculated by the Serpent Monte Carlo code and the newly released ENDF/B-VIII.0 nuclea
Externí odkaz:
https://doaj.org/article/a0bd8d9f802b4b12a6abb4c527d86a21
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 7, Pp 1729-1737 (2019)
This paper presents neutronics design of VVER-1000 fuel assembly using burnable poison particles (BPPs) for controlling excess reactivity and pin-wise power distribution. The advantage of using BPPs is that the thermal conductivity of BPP-dispersed f
Externí odkaz:
https://doaj.org/article/77ce013a724748be86c964d14f853010
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
Publikováno v:
Nuclear Engineering and Technology. 55:1775-1782
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 9
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). The Monte Carlo code Serpen
Publikováno v:
International Journal of Energy Research. 46:1327-1338
Publikováno v:
Atom Indonesia, Vol 46, Iss 1, Pp 33-39 (2020)
TheTRIGA 2000 reactor in Bandung is planned to change its fuel type from the TRIGA fuel rod type to the U 3 Si 2 -Al plate type of low enriched uranium of 19.75 % with uranium density of 2.96 gU/cc. A study on the neutronic parameters from the equili