نتایج جستجو برای: reactor core

تعداد نتایج: 242961  

2011
Amin Abedi Naser Vosoughi Mohammad Bagher Ghofrani

Double heterogeneity of randomly located pebbles in the core and Coated Fuel Particles (CFPs) in the pebbles are specific features in pebble bed reactors and usually, because of difficulty to model with MCNP code capabilities, are neglected. In this study, characteristics of HTR-10, Tsinghua University research reactor, are used and not only double heterogeneous but also truncated CFPs and Pebb...

1996
T. WU A. J. Lipps

The Advanced Liquid Metal Reactor (ALMR) is a US Department of Energy (DOE) sponsored fast reactor design based on the Power Reactor, Innovative Small Module (PRISM) concept originated by General Electric and fieled with ternary metal Iiel (under development by Argonne National Laboratory in the IFR Program). Higher actinide transmutation may be accomplished in the ALMR by using either a breedi...

Journal: :Journal of nuclear engineering 2021

In this paper, the conceptual design and a preliminary study of LUT Heating Experimental Reactor (LUTHER) for 2 MWth power are presented. Additionally, commercially sized designs 24 120 powers briefly discussed. LUTHER is scalable light-water pressure-channel reactor designed to operate at low temperature, pressure, core density. The utilizes enriched uranium (LEU) produce low-temperature outpu...

2012
B. SMODIŠ L. SNOJ

The 250 kW TRIGA Mark II research reactor of the Jožef Stefan Institute (JSI) has been in operation since 1966. The reactor went critical on 30 May 1966. It is a light water reactor, with solid fuel elements in which the zirconium hydride moderator is homogeneously distributed between enriched uranium. The reactor core consists of about 70 fuel elements, which are arranged in an annular lattice...

2012
Naoyuki Takaki

Our previous studies on water cooled thorium breeder reactor based on matured pressurized water reactor (PWR) plant technology concluded that reduced moderated core by arranging fuel pins in a triangular tight lattice array and using heavy water as coolant is appropriate for achieving better breeding performance and higher burn-up simultaneously [1–6]. One optimum core that produces 3.5 GW ther...

2007
S. A. Jonah G. I. Balogun A. I Obi Y. A. Ahmed B. Nkom A. A. Mati

The Nigeria Research Reactor-1 (NIRR-1) is the nation’s first nuclear reactor and it is sited at the Centre for Energy Research and Training, Ahmadu Bello University, Zaria, Nigeria. It is a Miniature Neutron Source Reactor (MNSR) that attained criticality on February 03, 2004 and was licensed to operate at a maximum power of 31 kW three days a week in June 01, 2004. This presentation enumerate...

2004
Wei Ji Jeremy L. Conlin William R. Martin

As part of an I-NERI project to develop safety analysis codes and experimental validation for a VeryHigh Temperature Gas-Cooled Reactor (VHTGR), we have developed MCNP5 [1] models to represent material heterogeneities inherent in the microsphere fuel particles and fuel compacts for a GT-MHR design [2]. We have also performed preliminary coupled nuclear-thermalhydraulic (NTH) analysis to obtain ...

2004
Daniel R. Parisi Miguel A. Laborde

In this work, the shaft furnace reactor of the MIDREX® process is simulated. This is a counter current gas-solid reactor, which transforms iron ore pellets into sponge iron. Simultaneous mass and energy balance along the reactor leads to a set of ordinary differential equation with two points boundary conditions. The iron ore reduction kinetics was modelated with the unreacted shrinking core mo...

2007
J. Rataj L. Sklenka

The Paper describes basic information about MCNP calculations and experimental measurements at the VR-1 reactor and their evaluation. The preparation of calculations and verification of the experiments are integral part of the VR-1 reactor operation. The neutronics calculations and analyses are often necessary condition to gain the approval to experiments realization at the reactor VR-1. The pa...

2012
R. Coulon S. Normand T. Domenech G. Corre T. Montagu T. Dautremer E. Barat

This work deals with the use of gamma spectrometry to monitor the fourth generation of sodium fast reactor (SFR) power. Simulation part has shown that power monitoring in short response time and with good accuracy is possible measuring liquid sodium delayed gamma emitters produced in-core. An experimental test is under preparation at French SFR Phénix experimental reactor to validate simulation...

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