Results 11 to 20 of about 2,420,955 (221)
Trudy Odesskogo Politehničeskogo Universiteta, 2017 The constant preparation issues are important for performing the few-group analysis for different states of the reactor core. Besides, the constant preparation method influences the further calculations accuracy and quality.
Віталій Володимирович Гальченко +2 more
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State and parameter estimation approach to monitoring AGR nuclear core [PDF]
, 2007 This work concerns with the problem of monitoring an Advanced Gas-cooled Nuclear Reactor (AGR) core. This plant (figure 1) makes use of the heat given by the nuclear efficient reaction to produce electricity by means of steam turbines.
Grimble, M.J. +4 more
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Eurasian Journal of Physics and Functional Materials, 2022 Nowadays, the WWR-K research reactor is operated with low-enriched uranium fuel and a beryllium neutron reflector. Irradiation positions located in the core make it possible to irradiate objects no larger than 50 mm in size.
A. A. Shaimerdenov +7 more
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Thermal-hydraulic calculations of the WWR-SM research reactor [PDF]
Ядерна фізика та енергетика, 2020 The paper presents calculations of the thermal power distribution in the reactor core (RC) of the WWR-SM research nuclear reactor of the Institute of Nuclear Physics of the Academy of Sciences of the Republic of Uzbekistan, settlement Ulugbek, Tashkent ...
S. A. Baytelesov +2 more
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Nuclear Engineering and Technology, 2018 Licenses for the storage of spent nuclear fuel (SNF) and vitrified highly active waste in casks under dry conditions are limited to 40 years and have to be renewed for prolonged storage periods.
Gerold Spykman
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Evaluation of fast fission factor in a typical pool type research reactor [PDF]
Journal of Nuclear Research and Applications, 2022 One of the important factors of a nuclear reactor core is the fast fission factor. This paper calculates this parameter based on space and energy-dependent method using the PTRAC card of MCNPX code. Tehran research reactor (TRR) is taken as a case study,
M. Arkani, S. Khakshournia
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FUEL BURN-UP CALCULATION FOR WORKING CORE OF THE RSG-GAS RESEARCH REACTOR AT BATAN SERPONG
Jurnal Penelitian Fisika dan Aplikasinya, 2017 The neutronic parameters are required in the safety analysis of the RSG-GAS research reactor. The RSG-GAS research reactor, MTR (Material Testing Reactor) type is used for research and also in radioisotope production.
Tukiran Surbakti, Mochammad Imron
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Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
Science and Technology of Nuclear Installations, 2012 In the framework of the OECD/NRC PSBT benchmark, the subchannel grade void distribution data and DNB data were assessed by a subchannel code, MATRA. The prediction accuracy and uncertainty of the zone-averaged void fraction at the central region of the 5
Dae-Hyun Hwang +3 more
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Analysis Loading Height of HTR (High Temperature Reactor) Core to Obtain Criticlity of Reactor
International Journal of Science and Engineering, 2015 High temperatur reactor (HTR) attract to be studied due to it has inherent safety characteristics and capabilities to produce energy economically. Design of reactor core in this study is a blend HTR 10 in China with HTR pebble-bed.
Evi Setiawati
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SENSITIVITY ANALYSIS OF STAINLESS STEEL REFLECTOR FOR VR-1 TRAINING REACTOR [PDF]
EPJ Web of Conferences, 2021 Pressurized water reactors are typically surrounded in the radial direction by neutron reflectors made from stainless steel and water. These reflectors decrease neutron leakage and provide protection of pressure vessel from fast neutrons damaging its ...
Frybort Jan +4 more
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