Text

ANALISIS NEUTRONIK TERAS CANDLE-GFR DENGANVARIASI BAHAN BAKAR MENGGUNAKAN PERANGKAT LUNAKOPENMC

---

Penilaian

---

This study analyzes the GFR core with a CANDLE burn up strategy with a variety of fuels, Uranium Carbide (UC) and Uranium Nitride (UN). UC and UN are used as starter fuel and natural uranium is used as fresh fuel. The simulation uses the Monte Carlo method in the OpenMC program and uses the ENDF/B-VIII.0 library. The calculated physical parameters are conversion ratio, effective multiplication factor, rate of fission reaction, and flux distribution. The effective multiplication factor to remain critical (k≧1) for both variations of fuel has an enrichment arrangement at UC of 12%, 8%, and 6.5% while for UN 13%, 9.25%, and 7.5%. There is a decrease in the composition of the fissile and fertile material, thereby reducing the risk of neutron leakage. Burn up using the CANDLE strategy has been successfully simulated with the burn up period of the starter fuel occurring in the first 20 years and continued with fresh fuel in the following year which can be seen from the rate of the fission reaction and the distribution of the flux. In addition, Uranium Carbide was tested for power variations of 600 MWth, 800 MWth, and 1000 MWth to determine changes in Keff, CR, and flux distribution.

---

Availability

Inventory Code	Barcode	Call Number	Location	Status
2207004260	T80437	T804372022	Central Library (Referens)	Available but not for loan - Not for Loan

Detail Information

Series Title

-

Call Number

T804372022

Publisher

Inderalaya : Jurusan fisika, Fakultas Matematika Dan Ilmu Pengetahuan Alam, Universitas Sriwijaya., 2022

Collation

xiii, 47 hlm.; ilus.; 29 cm

Language

Indonesia

ISBN/ISSN

-

Classification

531.307

Content Type

-

Media Type

-

Carrier Type

-

Edition

-

Subject(s)

Jurusan Fisika
Dinamika Benda Padat

Specific Detail Info

-

Statement of Responsibility

SEPTA

Other version/related

File Attachment

Comments

---

You must be logged in to post a comment