Pengolahan data nuklir endf/B-VI untuk kode komputer MCNP (Monte Carlo Neutral Particle) menggunakan paket program NJOY97,): pengujian melalui perhitungan angka kritis

S a w I y a h , S a w I y a h (2002) Pengolahan data nuklir endf/B-VI untuk kode komputer MCNP (Monte Carlo Neutral Particle) menggunakan paket program NJOY97,): pengujian melalui perhitungan angka kritis. Undergraduate thesis, FMIPA UNDIP.

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Abstract

Telah dilakukan proses pengolahan data tampang iintang reaksi nuklir sehingga menjadi data ACE Format dan dapat digunakan untuk menjalankan kode komputer Monte Carlo Neutral Particle (MCNP) dan MCNP yang digunakan untuk perhitungan angka kritis elemen bakar reaktor (30 MW). Proses pengolahan data ini dilakukan oleh kode komputer NJOY97.0. Data yang digunakan adalah ENDF (Evaluated Nuclear Data File) dan pengoperasian kode komputer ini dilakukan dengan personal computer pentium II. Kode komputer MCNP untuk menghitung angka kritis elemen bakar reaktor (30 MW) dilakukan dengan menggunakan personal computer pentium IV. Dari hasil pemrosesan oleh kode komputer NJOY97.0 diperoleh data dalam bentuk ACE Format, untuk 13 inti atom dan dari perhitungan menggunakan kode komputer MCNP diperoleh angka kritis untuk satu elemen bakar di dalam reaktor G. A. Siwabessy sebesar 1,0912. The data processing of the nuclear reaction cross section has been done. This data became ACEformat and it can be used to operate Monte Carlo Neutral Particle (MCNP) Computer Code. Criticallity Factor of reactor (30 MW) has been determined by using this Code. The data processing has been done by NJ0Y97.0 Code. The Evaluated Nuclear Data File (ENDF) was used and the operation of IVJOY97.0 was carried out by personal computer pentium 11. Furthermore, the computer code of Monte Carlo Neutral Particle (MCNP) has been used to calculate criticallity factor for fuel element of reactor (30 MW) and it has been done by using personal computer pentium IV. The result of the proccess using NJOY97.0 Code is ACE Format data for 13 nucleus and the value of criticallity factor for one fuel element in Reactor G.A. Siwabessy was found 1,0912. This document is Undip Institutional Repository Collection. The author(s) or copyright towner(s) agree that UNDIP-IR may, without changing the content, translate the nai s bmission to any medium or format for the purpose of preservation. The author(s) or copyright owner(s) also agree that UNDIP-IR may keep more than one copy of this s bmission for purposes of security, back-up and preservation. ( http://eprints.undip.ac.id)

Item Type:Thesis (Undergraduate)
Subjects:Q Science > QC Physics
Divisions:Faculty of Science and Mathematics > Department of Physics
ID Code:30335
Deposited By:Mr UPT Perpus 1
Deposited On:27 Oct 2011 11:07
Last Modified:27 Oct 2011 11:07

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