Determination of the Activity Inventory in the Structural Components of the Dalat Nuclear Research Reactor for Its Decommissioning Planning. (18th May 2022)

• Record Type: Journal Article
• Authors: Tran, Quoc-Duong; Nguyen, Kien-Cuong; Luong, Ba-Vien; Huynh, Ton-Nghiem; Pham, Quang-Huy; Vo, Doan-Hai-Dang; Nguyen, Nhi-Dien
• Other Names: Ivanov Peter Academic Editor.
• Is Part Of: Science and technology of nuclear installations. Volume 2022(2022)
• Publication Date: 2022-05-18
• Subjects: Nuclear engineering -- Periodicals; Nuclear facilities -- Periodicals; Nuclear engineering; Nuclear facilities; Electronic journals; Periodicals; 621.48
• DOI: 10.1155/2022/5174696
• Languages: English
• ISSNs: 1687-6075

Abstract

Abstract : This report presents the methods and calculated results of the activity inventory in the structural components of the Dalat Nuclear Research Reactor (DNRR). These components include the shielding concrete, the reactor tank, and its inside irradiated facilities; the thermal and thermalizing columns; and the horizontal channels. The MCNP5 code with a three-dimensional neutron transport model was used to calculate the neutron flux distribution, neutron energy spectrum at different locations, and activation cross sections of long-lived radioactive nuclides in activated major materials, including heavy concrete, reflection graphite, and aluminum of the reactor. The calculated results of the energy spectrum and activation cross sections of MCNP5 were used in the ORIGEN2.1 point depletion code to calculate the neutron-induced activity of activated materials at different time points by modeling the irradiation history and radioactive decay. Radioactivity of long-lived key activation products such as 41 Ca, 60 Co, 55 Fe, 63 Ni, and 152 Eu was modeled, and volumes of radioactive waste mainly of ordinary concrete, graphite, and aluminum in the structural components of the reactor were estimated. Experimental results of neutron flux and specific activities of some typical nuclides such as 60 Co, 152 Eu, 55 Fe, and 63 Ni in activated aluminum samples showed good agreement with the calculated results. As part of the national regulation requirements, the obtained data have been used to develop the decommissioning plan for the operational DNRR, with an estimation of about 10 years before its permanent shutdown.