Identification of thermal neutron flux in central thimble of TRIGA 2000 reactor with experimental method-Reference-Cited by-同舟云学术

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Identification of thermal neutron flux in central thimble of TRIGA 2000 reactor with experimental method

Published:2023 Issue: Volume: Page:
ISSN:0094-243X
Container-title:CHEMISTRY BEYOND BORDERS: INTERNATIONAL CONFERENCE ON PHYSICAL CHEMISTRY: The 1st Annual Meeting of the Physical Chemistry Division of the Indonesian Chemical Society
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Author:

Roswita Fahma,Seno Haryo,Basuki Prasetyo,Wafda Hakimul,Efendi Ahmad Mudzakir,Trianti Nuri

Publisher

AIP Publishing

Link

http://aip.scitation.org/doi/pdf/10.1063/5.0173580

Reference12 articles.

1. BATAN, Nyukcruk Galur BATAN Bandung. Bandung: BATAN Press, 2018.

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

3. E. Ratnawati, J. Iman, and H. Ali, “Evaluation of Thermal and Epithermal Neutron Fluxes at the RSG GAS Rabbit System Facility Terrace 89,” Bul. Pengelolaan Reakt. Nukl., vol. 13, 2016.

4. G. D. Bouchey, "Experimental Neutron Flux Measurements and Power Calibration in The Kansas State University Triga Mark II Nuclear Reactor," Kansas State University, 1967.

5. BATAN, “Safety Analysis Report of TRIGA 2000 Reactor No. R 093/KN 01 01/SNT 4,” Bandung, 2016.

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