Uji Kritikalitas dan Pengayaan Reaktor Air Superkritis (SCWR) dengan Bahan Bakar Uranium - Thorium (Criticality and Enrichment Supercritical Water Reactor (SCWR) With Uranium – Thorium Fuel)

Sunaryo, Meliana Selviani (2013) Uji Kritikalitas dan Pengayaan Reaktor Air Superkritis (SCWR) dengan Bahan Bakar Uranium - Thorium (Criticality and Enrichment Supercritical Water Reactor (SCWR) With Uranium – Thorium Fuel). Fakultas MIPA, Universitas Lampung.

[img]
Preview
Text
COVER DALAM.pdf - Published Version

Download (65Kb) | Preview
[img]
Preview
Text
ABSTRACT.pdf - Published Version

Download (113Kb) | Preview
[img]
Preview
Text
ABSTRAK.pdf - Published Version

Download (83Kb) | Preview
[img]
Preview
Text
HAL PENGESAHAN.pdf - Published Version

Download (82Kb) | Preview
[img]
Preview
Text
HAL PERSETUJUAN.pdf - Published Version

Download (98Kb) | Preview
[img]
Preview
Text
PERNYATAAN.pdf - Published Version

Download (40Kb) | Preview
[img]
Preview
Text
DAFTAR ISI.pdf - Published Version

Download (87Kb) | Preview
[img]
Preview
Text
BAB I.pdf - Published Version

Download (386Kb) | Preview
[img]
Preview
Text
BAB II.pdf - Published Version

Download (493Kb) | Preview
[img]
Preview
Text
BAB III.pdf - Published Version

Download (295Kb) | Preview
[img] Text
BAB IV.pdf - Published Version
Restricted to Registered users only

Download (445Kb)
[img]
Preview
Text
BAB V.pdf - Published Version

Download (45Kb) | Preview
[img]
Preview
Text
DAFTAR PUSTAKA.pdf - Published Version

Download (97Kb) | Preview
[img] Archive
LAMPIRAN.zip - Published Version

Download (427Kb)

Abstrak

Telah dilakukan penelitian untuk menguji kritikalitas dan pengayaan reaktor air superkritis (Super Critical Water Reactor) menggunakan bahan dasar thorium-uranium. Adapun tujuan dari penelitian ini antara lain mengetahui pengayaan (enrichment) U233 pada reaktor air superkritis (SCWR) agar reaktor berada dalam keadaan kritis ditunjukkan dengan nilai keff = 1,00000, mengetahui radius pin bahan bakar reaktor air superkritis (SCWR) untuk mendapatkan bentuk pembakaran yang efisien dan reaktor berada dalam keadaan kritis ditunjukkan dengan nilai keff = 1,00000, dan menganalisis pembiakan (breeding) reaktor yang ditunjukkan dengan meningkatnya densitas atom U233 setelah pembakaran. Penelitian ini menggunakan program untuk mendesain reaktor adalah SRAC ( Standard thermal Reactor Analysis Code). Data berupa radius pin bahan bakar dan ukuran moderator dihitung menggunakan PIJ dalam program SRAC. Hasil dari penelitian ini yaitu reaktor mencapai keadaan kritis pada pengayaan 3,6% dengan keff 0,991635, bila dibulatkan akan ~1,00000. Radius pin bahan bakar yang mendekati kritis yaitu pada radius 0,4219 dengan keff 1,004902. Sedangkan untuk ukuran moderator yang berada dalam keadaan kritis yaitu pada radius 0,7016 μm dengan keff 1,004978 masing-masing pada pembakaran hingga ~33009,5 MWd/ton. Terdapat densitas atom (atom/cm3) U233 dan Th232 serta produk fisi lain seperti U235, U238, dan Pu239. Dapat disimpulkan bahwa Keff dan pembakaran (MWd/ton) meningkat seiring dengan bertambahnya muatan U233 yang dimuat kedalam teras reaktor serta perluasan ukuran pin bahan bakar dan moderator. Reaktor pada penelitian ini tidak dapat disebut breeder karena mengalami penurunan densitas atom U233 setelah pembakaran dan mempunyai nilai BR<1. Kata kunci: kritikalitas, pengayaan, SCWR, kritis, pin bahan bakar, moderator, keff, breeder. (Research examined the criticality and enrichment supercritical water reactor (Super Critical Water Reactor) using thorium-uranium material has been done. The purposed of this study, knowing enrichment U233 on supercritical water reactor (SCWR) that the reactor is in a critical condition has indicated by the value of keff = 1,00000, knowing the fuel pin radius of supercritical water reactor (SCWR) to get burnup and efficient reactors were in critical condition indicated by the value of keff = 1,00,000, and analyzed breeding reactor has indicated by the increasing atomic density of U233 after burnup. This study are performed by a program to design the reactor SRAC code system. Data of fuel pin radius and moderators size is calculated by the PIJ in SRAC program. Results from this research that the reactor reached critical condition at 3.6% enrichment with keff 0.991635, if rounded to ~ 1,00000. Fuel pin radius who approached the critical is 0.4219 μm radius with keff 1.004902. The moderator who was in critical condition is 0.7016 μm radius with keff 1.004978, respectively burnup ~ 33009.5 MWD / ton. Atomic density of U233 and Th232 and other fission products such as U235, U238, and Pu239. It can be concluded that the keff and burnup (MWD / ton) increase with U233 is loaded into the reactor core and the expansion of the size of the fuel pin and moderator radius. Reactor in this study can not be called a breeder because U233 atomic density decreased after burnup and has a value of BR <1. Keywords: criticality, enrichment, SCWR, fuel pin, moderator, keff, breeder.)

Tipe Karya Ilmiah: Skripsi
Subyek: Q Science (General) > Q Science (General)
Q Science (General) > QC Physics
Program Studi: Fakultas MIPA > Prodi Fisika
Depositing User: Farid Hambali Prihantoro, A.Md.
Date Deposited: 03 Feb 2014 05:03
Last Modified: 03 Feb 2014 05:03
URI: http://digilib.unila.ac.id/id/eprint/876

Actions (login required)

View Item View Item