2016
DOI: 10.17146/tdm.2016.18.3.3022
|View full text |Cite
|
Sign up to set email alerts
|

Pengaruh Bentuk Routing Perpipaan Sistem Pendingin Primer Reaktor Triga Konversi Terhadap Penurunan Aktivitas N-16 Di Permukaan Tangki Reaktor

Abstract: ABSTRAK Program  konversi reaktor TRIGA 2000 Bandung dari bahan bakar silinder menjadi bahan bakar pelat perlu perancangan sistem  pendingin reaktor yang baru. Perancangan sistem pendingin reaktor yang baru  tersebut diusahakan tidak banyak mengalami perubahan dari sistem pendingin reaktor yang telah ada, mengingat ruang dan tempatnya tidak mungkin diubah. Oleh karena itu perlu dilakukan analisis untuk memilih routing perpipaan sistem pendingin reaktor TRIGA pelat yang dapat memenuhi persyaratan pendinginan si… Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
2
1

Citation Types

0
3
0

Year Published

2018
2018
2019
2019

Publication Types

Select...
3

Relationship

2
1

Authors

Journals

citations
Cited by 3 publications
(3 citation statements)
references
References 3 publications
(3 reference statements)
0
3
0
Order By: Relevance
“…4 as shown in Figure 4. Using the pump flow rate from thermohydraulic analysis results, subsequent calculation on the piping system length could obtain the velocity distribution in the pipe and used to predict the travel time of N-16 from the reactor core to the surface of reactor tank by the radioactivity decay equation [2]: The route selection of piping system coolant was then continued with pipe stress analysis, to ensure no failure in the piping system if various loads occurred during the reactor operation. In this case CAESAR II as a FEM (finite element method) based software was used to conduct analysis, based on ASME B31.1 Power Piping Code for industrial and commercial energy piping.…”
Section: Methodsmentioning
confidence: 99%
See 1 more Smart Citation
“…4 as shown in Figure 4. Using the pump flow rate from thermohydraulic analysis results, subsequent calculation on the piping system length could obtain the velocity distribution in the pipe and used to predict the travel time of N-16 from the reactor core to the surface of reactor tank by the radioactivity decay equation [2]: The route selection of piping system coolant was then continued with pipe stress analysis, to ensure no failure in the piping system if various loads occurred during the reactor operation. In this case CAESAR II as a FEM (finite element method) based software was used to conduct analysis, based on ASME B31.1 Power Piping Code for industrial and commercial energy piping.…”
Section: Methodsmentioning
confidence: 99%
“…This modification resulted in different core cooling process, due different heat distribution in the core. The direction of coolant flow in the reactor core changes from bottom-to-top natural convection to top-to-bottom forced convection, and this causes a change of the cooling fluid piping route [1,2].…”
Section: Introduction *mentioning
confidence: 99%
“…Whereas for the secondary cooling system can use the existing secondary cooling system of TRIGA 2000 Bandung reactor but it is necessary to re-analyze the cooling process. With the state of the new piping system, it is necessary to recalculate the pump power requirements that must be provided by the existing pump [6].…”
Section: Introductionmentioning
confidence: 99%