نتایج جستجو برای: fission reactor coolant

تعداد نتایج: 45549  

Journal: :HNPS Advances in Nuclear Physics 2023

During the almost seven decades of use nuclear fission for electric energy production two major accidents took place, i.e., 1986 Chernobyl accident and 2011 Fukushima one. They were caused by reactor power-surge loss-of-coolant, respectively. Both occurred during hot power shutdown had identical root causes, poor safety culture management in industry state authorities. A brief comparison facili...

2001
Hiroshi Takahashi

To run a high conversion reactor with Pu-Th fuelled tight fuelled assembly, which has a long burn-up of a fuel, the reactor should be sited deep underground. By putting the reactor deep underground heat can be removed passively not only during a steady-state run and also in an emergency case of loss of coolant and loss of on-site power; hence the safety of the reactor can be much improved. Also...

Ali Pazirandeh Meysam Mohammadnia Mohammad Hassan jalili bahabadi

The present work investigates an appropriate way to calculate the 1700 atomic density changes in the reactor operations. To automate this procedure, a computer program has been designed by C#. This program suggests a way to solve this problem which is based on the solution system of differential equations (Bitman) that it is designed according to Runge-Kutta Fehlberg method. The designed softwa...

2002
M. E. Sawan

A breeding blanket design for the tritium production ICF reactor SIRIUS-T is presented. The blanket consists of alternating layers of beryllium multiplier and lithium breeder/coolant with vanadium alloy structure. A tritium breeding ratio of 1.9 can be achieved for the optimum layered configuration with lithium enriched to 90% 6Li. An optimum coolant routing scheme is utilized to achieve adequa...

Journal: :Journal of Nuclear Science and Technology 2021

Researches on the fission product chemistry made after severe accident of Fukushima Daiichi Nuclear Power Station were reviewed with focus Cs in terms two regimes, namely, accidental source term and long-term via aqueous phase toward decommissioning. For term, chemical interaction Mo, B, Si under steam atmosphere greatly affect behavior release from fuel revaporization deposit structural materi...

2014
J. Marvin Herndon

The background, basis, feasibility, structure, evidence and geophysical implications of a naturally occurring Terracentric nuclear fission georeactor are reviewed. For a nuclear fission reactor to exist at the centre of the Earth, all of the following conditions must be met: (1) There must originally have been a substantial quantity of uranium within Earth’s core. (2) There must be a natural me...

Journal: :علوم و تکنولوژی پلیمر 0
حسین عابدینی محمد شاهرخی مهرسا امامی

the steps taken in designing a loop reactor for bulk propylene polymerization are discussed. the roles played by several parameters like particle growth factor, catalyst activity and solid fraction on reactor volume at different operating conditions are investigated. at first, based on a fixed production capacity and specific rate of catalyst, reactor volume is determined. next, the length and ...

2013
A. Hassanein T. Sizyuk

Plasma instability events such as disruptions, edge-localized modes (ELMs), runaway electrons (REs), and vertical displacement events (VDEs) are continued to be serious events and most limiting factors for successful tokamak reactor concept. The plasma-facing components (PFCs), e.g., wall, divertor, and limited surfaces of a tokamak as well as coolant structure materials are subjected to intens...

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...

Journal: :Journal of Nuclear Materials 2022

Outcomes of an activity on development and verification models for Fission Gas Release in Light-Water Reactor fuels during Loss-of-Coolant Accidents are described. The GRSW-A model the FALCON code is extended to simulate processes fuel fragmentation concomitant transient Release. FRELAX redesigned with a view simulation bulk flow diffusion gases rod free volume. Finally, close coupling updated ...

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