Results 11 to 20 of about 1,102,250 (263)
Validation of Neutron Flux and Activation in the Nagra AMAC model of the Mühleberg Power Plant [PDF]
The decommissioning of the Mühleberg Nuclear Power Plant (KKM) is supported by Nagra (National Cooperative for the Disposal of Radioactive Waste) through computational analysis of neutron activation in the reactor components and structures using the ...
Bykov Valentyn +3 more
doaj +1 more source
Efficient decontamination of 137Cs in electric arc furnace dust (EAFD) was carried out using a solid-liquid extraction method and then the obtained wastewater contaminated with 137Cs was treated by a co-precipitation. The influences of pH, stirring time,
P. Sopapan +6 more
doaj +1 more source
Electrochemical Properties of NdCl3 and CeCl3 in Molten LiCl-KCl Eutectic Salt
NdCl3 and CeCl3 are characterized by the very close proximity of their standard reduction potentials. Thus, they represent the most challenging salt mixtures with respect to decoupling electrochemical responses and calculating concentrations.
Seunghyun Kim, Sang-hwan Lee
doaj +1 more source
Proposed Managements of 137Cs Contaminated Soil: Case Study in South Tangerang City
Recently, BAPETEN found contamination of 137Cs while testing environmental radiation monitoring equipment in an area in South Tangerang City. The area, therefore, needs to be cleaned up by performing decontamination followed by the activity of treating ...
B. Setiawan +9 more
doaj +1 more source
Near-field/far-field interface of a near-surface low level radioactive waste site [PDF]
Experimental and Modelling studies have been used to investigate the biogeochemical processes occurring at the interface zone between the near-field and far-field of the Drigg Low- Level radioactive Waste (LLW) trenches.
Hand, V. L. +6 more
core +4 more sources
Measuring thermal conductivity and water suction for variably saturated bentonite
An engineered barrier system (EBS) for the disposal of high-level radioactive waste (HLW) is composed of a disposal canister with spent fuel, a buffer material, a gap-filling material, and a backfill material.
Seok Yoon, Geon-Young Kim
doaj +1 more source
Parallel groundwater flow simulation method based on a discrete fracture network model
Objective Groundwater flow in fractured rocks has strong heterogeneity and anisotropy. The discrete fracture network (DFN) method has been internationally considered as one of the most reasonable and effective methods to describe the fracture water ...
Jingbo Zhao +5 more
doaj +1 more source
Experimental approach for understanding the dynamic behaviors of bentonite buffer piping erosion
In Japan, as in other countries, bentonite-based buffer materials are expected to play roles in reducing stress from rock masses and mitigating nuclide migration in the geological disposal of high-level radioactive waste.
Tomoko ISHII +3 more
doaj +1 more source
This paper presents the results of various benefit–cost ratio (BCR) analyses of back-end nuclear fuel cycle alternatives. Korea is currently considering two alternatives for the disposal of spent nuclear fuel: direct disposal and pyroprocessing.
Sungki Kim, Jin-Seop Kim, Dong-Keun Cho
doaj +1 more source
The estimation of hydraulic and mechanical properties of bedrock is important for the evaluation of energy-related structures, including high-level nuclear waste repositories, hydraulic fracturing wells, and gas-hydrate production wells.
Ji-Won Kim +3 more
doaj +1 more source

