Seminarium Zakładu Energetyki Jądrowej i Analiz Środowiska

Positron Annihilation as a tool to study defects in Silicon Carbide

Silicon Carbide has been considered for use in Dual Fluid Reactor (DFR) as a construction material. Very good understanding of behaviour SiC during irradiation at high temperature is a key to safety and long term operation of DFR. The evolution of defects during irradiation and annealing to define the repair mechanism is still under study. Positron annihilation is one of the method which can be used to investigate the evaluation of defects in the irradiated SiC.

 

Modeling Fully Ceramic Microencapsulated (FCM) fuel – description of the research objectives

Good understanding of the failure-free performance of Tri-structural ISOtropic (TRISO)-particle fuel is a key for the safe and efficient operation of High Temperature Gas-cooled Reactors. One of the experimental method as a tool to investigate damage occurring in TRISO fuel is Raman spectroscopy. This method can be used to find damage in small particles of TRISO fuel at the front-end stage and during irradiation in the reactor. This seminar will focus on the description of the Raman method and on presenting the assumptions for an experiment on TRISO particles using the mentioned method.

MCORD - The MPD Cosmic Ray Detector - present status of work

At the Join Institute for Nuclear Research (Dubna, Russia), a new large research device - the NICA Collider - has been under construction for several years. An additional cosmic ray detector (MCORD) is designed for the main detector set (MPD). This detector, in addition to the obvious function of detecting cosmic ray particles, would be nice to improve recognition (detection) of muons from the collision and to work as an additional trigger for other sub-detectors. The MCORD detector elements are also to be used to calibrate other detectors before starting the beam.

Analytical design of the direct current magnetohydrodynamic pump

 

In the Dual Fluid Reactor (DFR) plants, there are two separated loops in which liquid metals, Uranium-Chromium eutectic as fuel and lead as a coolant will flow. Due to the high operating temperature of DFR, special contact-free pumps have to be applied. The best solution seems to be a magnetohydrodynamic pumping system which can utilize magnetic and electric fields acting on the metallic flow.

Reliability and Availability Analysis of the HTTR Electrical Facility

Driven by the desire to expand the industrial applications of high temperature gas-cooled reactors (HTGR) the Japan Atomic Energy Agency (JAEA) is intensively conducting research and development activities on the new commercial design of Gas Turbine High Temperature Reactor for Cogeneration (GTHTR300C). In order to confirm operation and safety performance of such a system for electricity and hydrogen cogeneration, the pre-licensing design of the test plant has been recently proposed that is based on the existing JAEA’s technology – High Temperature Engineering Test Reactor (HTTR).

Failure Mode and Reliability Analysis of the HTTR Electrical Facility

The first-of-a-kind commercial electricity and hydrogen cogeneration system are being designed by the Japan Atomic Energy Agency (JAEA) to establish the industrial application of high-temperature gas-cooled reactors (HTGR). The High Temperature Engineering Test Reactor (HTTR) is expected to be coupled with a test cogeneration plant in order to prove safety features and justify further HTGR technology development. The National Centre for Nuclear Research (NCBJ) initiated activities on reliability analysis of such a combined nuclear/non-nuclear facility.

Quantification of initiating events probability based on fragility functions and Bayesian network applied for multi-hazard

There are many ways to quantify initiating event probability and most of them are described in the document “Defining initiating events for purposes of probabilistic safety assessment”, developed by the International Atomic Energy Agency. This guide describes seven methods: engineering evaluation or technical study of a plant; reference to previous probabilistic safety assessment; EPRI list of initiating events; logical classification; plant energy balance fault tree; analysis of operation experience for an actual plant; failure mode and effect analysis.

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