Results 31 to 40 of about 2,311,049 (401)
Antineutrino flux from the Laguna Verde Nuclear Power Plant [PDF]
, 2015 We present a calculation of the antineutrino flux produced by the reactors at the Laguna Verde Nuclear Power Plant in M\'exico, based on the antineutrino spectra produced in the decay chains of the fission fragments of the main isotopes in the reactor ...
Aguilar-Arevalo, Alexis A. +1 more
core +3 more sources
Analysis of gamma ray dose for dried up pond storing low enriched UO2 fuel
EPJ Web of Conferences, 2017 Gamma ray dose is calculated for loss of coolant accident in spent fuel pond (SFP) storing irradiated fuels used in light water reactors. Influence of modelling of fuel assemblies, source distributions, and loading fraction of fuel assemblies in the fuel
Nauchi Yasushi, Suzuki Motomu
doaj +1 more source
Brazilian Journal of Radiation Sciences, 2019 A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel ...
Claubia Pereira +4 more
doaj +1 more source
Results of validation and cross-verification of the ROK/B design code on the problem of loss of cooling in the spent fuel pool [PDF]
Nuclear Energy and Technology, 2022 The procedures of validation and cross-verification of the newly developed computational code ROK/B are described. The main problem solved using the ROK/B code is the substantiation by calculation of the coolant density in the spent fuel pool (SFP) and ...
Ruslan M. Sledkov +4 more
doaj +3 more sources
Nuclear Engineering and Design, 2019 Accurate knowledge of the mechanical behaviour of the reactor core is needed to estimate the effects of a seismic excitation on a nuclear power plant.
R. Capanna +3 more
semanticscholar +1 more source
Effect of the burnable absorber arrangement on the VVER-1200 fuel assembly neutronic performance [PDF]
Nuclear Energy and Technology, 2021 Optimizing the use of fuel in a power reactor is a task of current concern. However, little attention has been given to investigating the dependences among the enrichment used, the content of gadolinium oxide in fuel elements, and the life time in ...
Ruslan A. Vnukov +4 more
doaj +3 more sources
MIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA
Acta Polytechnica CTU Proceedings, 2018 This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisting of fuel assemblies with non-identical spacing grids.
Vojtěch Caha, Jiří Čížek
doaj +1 more source
Size-Dependent Tile Self-Assembly: Constant-Height Rectangles and Stability [PDF]
, 2015 We introduce a new model of algorithmic tile self-assembly called size-dependent assembly. In previous models, supertiles are stable when the total strength of the bonds between any two halves exceeds some constant temperature.
Andrew Winslow +3 more
core +1 more source
Title Investigation of the influence of various factors on the power of heat exchange by radiation
Trudy Odesskogo Politehničeskogo Universiteta, 2017 The issue of lack of knowledge of radiation heat transfer process has been repeatedly raised in various studies. Despite the fact that works on study of heat transfer by radiation covers a wide range of different industries, it should be noted the lack ...
Korolyov Alexander V. +1 more
doaj +1 more source
Detection of Anomalous Reactor Activity Using Antineutrino Count Rate Evolution Over the Course of a Reactor Cycle [PDF]
, 2010 This paper analyzes the sensitivity of antineutrino count rate measurements to changes in the fissile content of civil power reactors. Such measurements may be useful in IAEA reactor safeguards applications. We introduce a hypothesis testing procedure to
Bulaevskaya, Vera, Bernstein, Adam
core +1 more source