Cite Article

The Study of Floating Nuclear Power Plant Reactor Core Neutronic Parameters Using Scale 6.1 Code

Choose citation format

BibTeX

@article{IJASEIT6609,
   author = {Dhirar Faisal Fajri and Alexander Agung and Andang Widi Harto},
   title = {The Study of Floating Nuclear Power Plant Reactor Core Neutronic Parameters Using Scale 6.1 Code},
   journal = {International Journal on Advanced Science, Engineering and Information Technology},
   volume = {10},
   number = {5},
   year = {2020},
   pages = {1774--1783},
   keywords = {floating nuclear power plant; KLT-40S; silumin alloy; SCALE 6.1.},
   abstract = {

KLT-40S nuclear reactor is a small modular floating nuclear power plant made by Russia as a conventional light water reactor (LWR) problem solution nowadays, such as high overnight cost, long commissioning period, and lack of flexibility in supplying a small load of electricity and supplying electricity to isolated areas. With those characteristics, the KLT-40S is suitable to be applied to isolated areas with a small electrical load like archipelagic states such as Indonesia. Based on that reason, Indonesia needs to assess the KLT-40S floating nuclear power plant feasibility study through explorative research. One of those is assessing the reactor core neutronic parameter. In this research, the reactor core modelling is done by using the KENO VI-A and T-6DEPL module in SCALE 6.1 code package. Several variations of reactor operating parameters such as fuel composition and configuration, fuel temperature, moderator temperature, and moderator void fraction had been done in this research. The aim was to get several neutronic parameters to confirm the core feasibility from operational and inherent safety perspectives. Those neutronic parameters are fuel cycle length and reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction. Based on this research result, the fuel configuration that produces 28 months of cycle length is the fuel base of dispersed UO2 in the silumin matrix with 18,6 % 235U enrichment. Both of the two fuel bases used in this research have inherent safety characteristics, which are shown by the negative value of the reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction.  Dispersed UO2 in the silumin matrix fuel base has better inherent safety characteristics than the UO2 ceramic metal fuel base.

},    issn = {2088-5334},    publisher = {INSIGHT - Indonesian Society for Knowledge and Human Development},    url = {http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=6609},    doi = {10.18517/ijaseit.10.5.6609} }

EndNote

%A Fajri, Dhirar Faisal
%A Agung, Alexander
%A Harto, Andang Widi
%D 2020
%T The Study of Floating Nuclear Power Plant Reactor Core Neutronic Parameters Using Scale 6.1 Code
%B 2020
%9 floating nuclear power plant; KLT-40S; silumin alloy; SCALE 6.1.
%! The Study of Floating Nuclear Power Plant Reactor Core Neutronic Parameters Using Scale 6.1 Code
%K floating nuclear power plant; KLT-40S; silumin alloy; SCALE 6.1.
%X 

KLT-40S nuclear reactor is a small modular floating nuclear power plant made by Russia as a conventional light water reactor (LWR) problem solution nowadays, such as high overnight cost, long commissioning period, and lack of flexibility in supplying a small load of electricity and supplying electricity to isolated areas. With those characteristics, the KLT-40S is suitable to be applied to isolated areas with a small electrical load like archipelagic states such as Indonesia. Based on that reason, Indonesia needs to assess the KLT-40S floating nuclear power plant feasibility study through explorative research. One of those is assessing the reactor core neutronic parameter. In this research, the reactor core modelling is done by using the KENO VI-A and T-6DEPL module in SCALE 6.1 code package. Several variations of reactor operating parameters such as fuel composition and configuration, fuel temperature, moderator temperature, and moderator void fraction had been done in this research. The aim was to get several neutronic parameters to confirm the core feasibility from operational and inherent safety perspectives. Those neutronic parameters are fuel cycle length and reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction. Based on this research result, the fuel configuration that produces 28 months of cycle length is the fuel base of dispersed UO2 in the silumin matrix with 18,6 % 235U enrichment. Both of the two fuel bases used in this research have inherent safety characteristics, which are shown by the negative value of the reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction.  Dispersed UO2 in the silumin matrix fuel base has better inherent safety characteristics than the UO2 ceramic metal fuel base.

%U http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=6609 %R doi:10.18517/ijaseit.10.5.6609 %J International Journal on Advanced Science, Engineering and Information Technology %V 10 %N 5 %@ 2088-5334

IEEE

Dhirar Faisal Fajri,Alexander Agung and Andang Widi Harto,"The Study of Floating Nuclear Power Plant Reactor Core Neutronic Parameters Using Scale 6.1 Code," International Journal on Advanced Science, Engineering and Information Technology, vol. 10, no. 5, pp. 1774-1783, 2020. [Online]. Available: http://dx.doi.org/10.18517/ijaseit.10.5.6609.

RefMan/ProCite (RIS)

TY  - JOUR
AU  - Fajri, Dhirar Faisal
AU  - Agung, Alexander
AU  - Harto, Andang Widi
PY  - 2020
TI  - The Study of Floating Nuclear Power Plant Reactor Core Neutronic Parameters Using Scale 6.1 Code
JF  - International Journal on Advanced Science, Engineering and Information Technology; Vol. 10 (2020) No. 5
Y2  - 2020
SP  - 1774
EP  - 1783
SN  - 2088-5334
PB  - INSIGHT - Indonesian Society for Knowledge and Human Development
KW  - floating nuclear power plant; KLT-40S; silumin alloy; SCALE 6.1.
N2  - 

KLT-40S nuclear reactor is a small modular floating nuclear power plant made by Russia as a conventional light water reactor (LWR) problem solution nowadays, such as high overnight cost, long commissioning period, and lack of flexibility in supplying a small load of electricity and supplying electricity to isolated areas. With those characteristics, the KLT-40S is suitable to be applied to isolated areas with a small electrical load like archipelagic states such as Indonesia. Based on that reason, Indonesia needs to assess the KLT-40S floating nuclear power plant feasibility study through explorative research. One of those is assessing the reactor core neutronic parameter. In this research, the reactor core modelling is done by using the KENO VI-A and T-6DEPL module in SCALE 6.1 code package. Several variations of reactor operating parameters such as fuel composition and configuration, fuel temperature, moderator temperature, and moderator void fraction had been done in this research. The aim was to get several neutronic parameters to confirm the core feasibility from operational and inherent safety perspectives. Those neutronic parameters are fuel cycle length and reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction. Based on this research result, the fuel configuration that produces 28 months of cycle length is the fuel base of dispersed UO2 in the silumin matrix with 18,6 % 235U enrichment. Both of the two fuel bases used in this research have inherent safety characteristics, which are shown by the negative value of the reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction.  Dispersed UO2 in the silumin matrix fuel base has better inherent safety characteristics than the UO2 ceramic metal fuel base.

UR - http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=6609 DO - 10.18517/ijaseit.10.5.6609

RefWorks

RT Journal Article
ID 6609
A1 Fajri, Dhirar Faisal
A1 Agung, Alexander
A1 Harto, Andang Widi
T1 The Study of Floating Nuclear Power Plant Reactor Core Neutronic Parameters Using Scale 6.1 Code
JF International Journal on Advanced Science, Engineering and Information Technology
VO 10
IS 5
YR 2020
SP 1774
OP 1783
SN 2088-5334
PB INSIGHT - Indonesian Society for Knowledge and Human Development
K1 floating nuclear power plant; KLT-40S; silumin alloy; SCALE 6.1.
AB 

KLT-40S nuclear reactor is a small modular floating nuclear power plant made by Russia as a conventional light water reactor (LWR) problem solution nowadays, such as high overnight cost, long commissioning period, and lack of flexibility in supplying a small load of electricity and supplying electricity to isolated areas. With those characteristics, the KLT-40S is suitable to be applied to isolated areas with a small electrical load like archipelagic states such as Indonesia. Based on that reason, Indonesia needs to assess the KLT-40S floating nuclear power plant feasibility study through explorative research. One of those is assessing the reactor core neutronic parameter. In this research, the reactor core modelling is done by using the KENO VI-A and T-6DEPL module in SCALE 6.1 code package. Several variations of reactor operating parameters such as fuel composition and configuration, fuel temperature, moderator temperature, and moderator void fraction had been done in this research. The aim was to get several neutronic parameters to confirm the core feasibility from operational and inherent safety perspectives. Those neutronic parameters are fuel cycle length and reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction. Based on this research result, the fuel configuration that produces 28 months of cycle length is the fuel base of dispersed UO2 in the silumin matrix with 18,6 % 235U enrichment. Both of the two fuel bases used in this research have inherent safety characteristics, which are shown by the negative value of the reactivity feedback coefficient of fuel temperature, moderator temperature, and moderator void fraction.  Dispersed UO2 in the silumin matrix fuel base has better inherent safety characteristics than the UO2 ceramic metal fuel base.

LK http://ijaseit.insightsociety.org/index.php?option=com_content&view=article&id=9&Itemid=1&article_id=6609 DO - 10.18517/ijaseit.10.5.6609