Zobrazeno 1 - 10
of 87
pro vyhledávání: '"SER GI HONG"'
Autor:
Sang-Kyung Lee, Ser Gi Hong
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1372-1384 (2024)
The discrimination of the source for xenon gases' release can provide an important clue for detecting the nuclear activities in the neighboring countries. In this paper, three machine learning techniques, which are logistic regression, support vector
Externí odkaz:
https://doaj.org/article/10e61a83e8ec49ca953c1ec3e30ff8f6
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1398-1406 (2024)
The control rod worth is a key safety parameter required to be measured in commercial pressurized water reactors (PWRs). Conventionally, the control rod worth is measured after reaching the critical state, which occupies the considerable time in the
Externí odkaz:
https://doaj.org/article/35d6051070bd4fadbb64a3483785351c
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 2, Pp 601-610 (2024)
This paper gives an extensive analysis on the characterization of xenon isotopic ratios for various nuclear reactors and nuclear explosions through neutronic depletion codes. The results of the characterization can be used for discriminating the sour
Externí odkaz:
https://doaj.org/article/23468c93e06042409c9770bbf23f1833
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4722-4730 (2022)
This paper introduces a new point depletion-based source term calculation code named BESNA (Bateman Equation Solver for Nuclear Applications), which is aimed to estimate nuclide inventories and source terms from spent nuclear fuels. The BESNA code em
Externí odkaz:
https://doaj.org/article/fd01dbbbe9dc431fa06ee39280ebd936
Autor:
MyeongHyeon Woo, Ser Gi Hong
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 11, Pp 4280-4295 (2022)
In this paper, a new multi-group neutron-gamma transport calculation code system STRAUM-MATXST for complicated geometrical problems is introduced and its development status including numerical tests is presented. In this code system, the MATXST (MATX
Externí odkaz:
https://doaj.org/article/6e85c095d5d240a880c83a3a638efdfb
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 11, Pp 3517-3527 (2021)
New 80-MW (electric) ultra-long-life sodium cooled fast reactor core having inherent safety characteristics is designed with heterogeneous fuel assemblies comprised of driver and blanket fuel rods. Several options using upper sodium plenum and SSFZ (
Externí odkaz:
https://doaj.org/article/2900bc2147cb46e69e6cbee258c3a2f8
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 1, Pp 19-29 (2021)
This paper presents the validation of the MCS code for critical safety analysis with burnup credit for the spent fuel casks. The validation process in this work considers five critical benchmark problem sets, which consist of total 80 critical experi
Externí odkaz:
https://doaj.org/article/87ddfc208f924e888cc5674f2daae1c0
Autor:
Ye Seul Cho, Ser Gi Hong
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 4, Pp 689-699 (2020)
In this work, new multi-recycling options of TRU nuclides using PWR fuel assemblies comprised of MOX and FCM (Fully Ceramic Micro Encapsulated) fuels are suggested and neutronically analyzed. These options do not use a fully recycling of TRU but a pa
Externí odkaz:
https://doaj.org/article/9b8b0ec882b140cf83738ff6aecb2c8f
Autor:
Habib Muhammad, Ser Gi Hong
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 3, Pp 485-498 (2020)
A diffusion synthetic acceleration (DSA) technique for the SN transport equation discretized with the linear discontinuous expansion method with subcell balance (LDEM-SCB) on unstructured tetrahedral meshes is presented. The LDEM-SCB scheme solves th
Externí odkaz:
https://doaj.org/article/139bbc4fdb4547f084a4a1e74bdc366f
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 1, Pp 13-30 (2019)
This paper presents the recent improvements in the DeCART code for HTGR analysis. A new 190-group DeCART cross-section library based on ENDF/B-VII.0 was generated using the KAERI library processing system for HTGR. Two methods for the eigen-mode adjo
Externí odkaz:
https://doaj.org/article/52dd2b419fbc4e7b9b78bedb6694bea2