Burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1 [PDF]
, 2011 The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, reference operating core, has been carried out utilizing standard computer codes WIMS/D4, CITATION, and RELAP5/MOD3.4.
Iqbal Masood +2 more
core +1 more source
Reprocessing Exhaust Gas Xenon Isotope Correlation Spent Fuel Burn-Up Based on ORIGEN Code
He huaxue yu fangshe huaxueEnvironmental sampling analysis technology is one of the safeguards measures used by International Atomic Energy Agency to detect undeclared nuclear materials and nuclear activities.
Sheng-hui HUANG +5 more
doaj +1 more source
Thermonuclear burn-up in deuterated methane $CD_4$
, 2010 The thermonuclear burn-up of highly compressed deuterated methane CD$_4$ is considered in the spherical geometry. The minimal required values of the burn-up parameter $x = \rho_0 \cdot r_f$ are determined for various temperatures $T$ and densities ...
Alexei M Frolov +9 more
core +1 more source
Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study [PDF]
, 2010 In this paper, we assess the impact of activation cross-section uncertainties on relevant fuel cycle parameters for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) with a “double strata” fuel cycle.
Aliberti +10 more
core +2 more sources
Determination of dose rate during the inspection of spent fuel element in the testing cell
Brazilian Journal of Radiation Sciences, 2020 Testing cell a hot cell is responsible for inspecting the spent fuel elements in open pool type reactor. Because the spent fuel elements examination in the testing cell would result in rising in radiation dose level, a previous precaution should be ...
Amr Abdelhady
doaj +1 more source
Comparisons of Reduced Moderation Small Modular Reactors With Heavy Water Coolant
Frontiers in Energy Research, 2020 This article presents the comparison of two reduced moderation small modular reactor concepts with heavy water coolant. Two reduced moderation small modular reactors, RMSMR-Th and RMSMR-MOX, are proposed for the sustainable utilization of nuclear ...
Tengfei Zhang +3 more
doaj +1 more source
Characterization Of Cladding Hull Wastes From Used Nuclear Fuels
Archives of Metallurgy and Materials, 2015 Used cladding hulls from pressurized water reactor (PWR) are characterized to provide useful information for the treatment and disposal of cladding hull wastes.
Kang K.H. +5 more
doaj +1 more source
Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction [PDF]
, 2015 The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository.
Casas Pons, Ignasi +4 more
core +2 more sources
Design and Optimization of Ram Air–Based Thermal Management Systems for Hybrid-Electric Aircraft
Aerospace, 2020 Ram air–based thermal management systems (TMS) are investigated herein for the cooling of future hybrid-electric aircraft. The developed TMS model consists of all components required to estimate the impacts of mass, drag, and fuel burn on the aircraft ...
Hagen Kellermann +3 more
doaj +1 more source
Evaluation of the neutronic performance of a fast traveling wave reactor in the Th-U fuel cycle [PDF]
Nuclear Energy and Technology, 2020 The possibility for all of the uranium or thorium fuel to be used nearly in full is expected in traveling wave reactors. A traveling wave reactor core with a fast neutron spectrum in a thorium-uranium cycle has been numerically simulated.
Alina Ye. Pomysukhina +2 more
doaj +3 more sources