Neutronic analysis for fresh instrumented fuel element ID 9884 type 204 with 8.5 wt% position in existing Bandung TRIGA 2000 core

Author:

Irsyad ,Basuki Prasetyo,Nailatussaadah ,Mediawan Anton

Publisher

AIP Publishing

Reference8 articles.

1. Analysis of TRIGA 2000 Core Reshuffling Scenario Based on Fuels Burn up and Fuels Density

2. CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

3. M. H. Rabir et. al., “Modelling The PUSPATI TRIGA Reactor Using MCNP Code”, (Research and Development Seminar, Bangi, 2012).

4. P Basuki, “Kajian Keselamatan Skenario Reshuffling Ulang dan Refueling Teras TRIGA 2000 No. R 192/RN 00 01/ SNT 4”, (BATAN, Bandung, 2019).

5. Anonim. Laporan Analisis Keselamatan Reaktor TRIGA 2000”, No. R 093/KN 01 01/SNT 4, (BATAN, Bandung, 2016).

Cited by 1 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Identification of thermal neutron flux in central thimble of TRIGA 2000 reactor with experimental method;CHEMISTRY BEYOND BORDERS: INTERNATIONAL CONFERENCE ON PHYSICAL CHEMISTRY: The 1st Annual Meeting of the Physical Chemistry Division of the Indonesian Chemical Society;2023

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