نتایج جستجو برای: fission reactor coolant

تعداد نتایج: 45549  

2002
H. Y. Khater M. E. Sawan

A detailed safety analysis was performed for the inertial confinement fusion reactor OSIRIS. The radioactivity induced in the carbon fabric chamber concrete shield and Flibe breeder is very low allowing for their disposal at the end of the reactor life as Class A low level waste (LLW). The biological dose rate after shutdown behind the reactor biological shield shield is very low (0.11 μ rem/hr...

2012
A. Dehbi S. Martin Paul Scherrer

The Generation IV Pebble Bed Modular Reactor (PBMR) is being considered as a promising concept to produce electricity or process heat with high efficiencies and unique safety features. The PBMR is a high-temperature, helium-cooled, graphite moderated reactor. The fuel elements consist of 6 cm diameter spherical graphite “pebbles” containing each thousands of uranium dioxide microspheres. As the...

2006
M. J. Brown

The Modular Accident Analysis Program for CANDU (MAAP4-CANDU) was developed to assess the consequences of a severe core damage progression in a CANDU nuclear power station. The results from MAAP4-CANDU analyses support Level 2 PSA activities being performed for CANDU stations. During the early stages of a severe core damage accident in a CANDU plant, the primary heat transport system (PHTS) coo...

Journal: :Frontiers in Energy Research 2022

The production and release of fission products in fuel rods the primary coolant have been simulated by kinetic model during normal operation a pressurized water reactor. typical ratio I-131/I-133 has theoretically estimated at equilibrium conditions for intact fuels failure with small or large defects, respectively. radiochemical data loops gathered compiled from thirty-six cycles operating CPR...

2005
Per F. Peterson

The AHTR is a pool-type reactor with graphite matrix coated-particle fuel and a clean molten salt coolant [1]. Due to the very high thermal inertia provided by the pool configuration and molten-salt coolant of the AHTR, the thermal power of the AHTR can be substantially higher than an equivalent gas-cooled reactor, likely exceeding 2000 MW(t). The AHTR, with a molten-salt intermediate loop and ...

Journal: :Epj Web of Conferences 2021

Sensitivity analysis studies the effect of a change in given parameter to response function system under investigation. In reactor physics, this usually translates into study how cross sections and fission spectrum modifications affect value multiplication factor, delayed neutron fraction or void coefficient for example. Generalized Perturbation Theory provides useful tool assessment adjoint we...

2014
Monika Bakošová Juraj Oravec

The continuous stirred-tank reactor with uncertain parameters was stabilized in the open-loop unstable steady state using the robust model predictive control. The gain matrices of the robust state-feedback controller were designed using the nominal system optimization and the quadratic parameter-dependent Lyapunov functions. The controller was verifi ed by simulations using the non-linear model...

2013
K Hema

Stable power processes are never guaranteed. An assortment of unstable behaviors wrecks power apparatus, including mechanical vibration, malfunctioning control apparatus, unstable fluid flow, unstable boiling of liquids, or combinations thereof. A necessary condition for stable reactor power is that the reactor distortion accompanying a temperature rise decreases the reactivity, thus slowing an...

1999
MOHAMED EL-GENK HUIMIN XUE CHRIS MURRAY

Practical application of thermionic space nuclear power systems necessitates the investigation of such systems responses to changes in operation and design parameters as well as load-following characteristics. The principle building block in these systems is the thermionic fuel element (TFE). A Thermionic Transient Analysis Model (TUAM) is developed to simulates transient and steady-state opera...

2013
A. Burger R. T. Dobson

R & D Journal of the South African Institution of Mechanical Engineering 2012,28,25-30 http://www.saimeche.org.za (open access) © SAIMechE All rights reserved. 25 The Pebble Bed Modular Reactor (PBMR) is a Generation IV graphite-moderated helium cooled nuclear reactor developed in South Africa from the German Arbeitsgemeinschaft Versuchreaktor (AVR). After decommissioning of the AVR plant, radi...

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