This paper describes the preliminary analysis of LOFA (loss of flow accident) and LOCA (loss of coolant accident) in the TIBER-II engineering test reactor breeding shield. TIBER-II is a compact reactor with a major radius of 3 m and thus requires a thin, ...

This report presents the thermal-hydraulic analysis of three Loss-of-Flow Accidents (LOFAs) in the first wall cooling system of the Next European Torus (NET) design or the International Thermonuclear Experimental Reactor (ITER) design. The LOFAs considere...

This report presents the thermal-hydraulic analysis of four Loss-of-Flow Accidents (LOFAs) in the first wall/blanket cooling system of the alternative SEAFP reactor design. The LOFAs considered result from a loss of electrical power for the recirculation ...

This report is one of a series of reports that document normal operation and accident simulations for the Accelerator Production of Tritium (APT) blanket heat removal system. These simulations were performed for the Preliminary Safety Analysis Report.

Within the framework of safety analysis for the next European torus, a decay heat hazards assessment is under way in Ispra. Undercooling accidents (loss-of-coolant and loss-of-flow accidents (LOCAs and LOFAs)) due to pump failure have been investigated assuming an automatic plasma shutdown in both cases. The ...

This paper describes the preliminary analysis of LOFA (loss of flow accident) and LOCA (loss of coolant accident) in the TIBER-II engineering test reactor breeding shield. TIBER-II is a compact reactor with a major radius of 3 m and thus requires a thin, high efficiency shield on the inboard side. The use of ...

This report is one of a series of reports that document normal operation and accident simulations for the Accelerator Production of Tritium (APT) blanket heat removal system. These simulations were performed for the Preliminary Safety Analysis Report. This report documents the results of simulations of a Loss-of-Flow Accident ...

The response of liquid metal self-cooled fusion reactors to a loss of flow accident (LOFA) is investigated. Coolant temperature rise through the blanket was determined for conditions where decay heat is removed solely by natural convection. It is found that lithium-lead (Li17-Pb83) coolant provides sufficient natural convection to remove decay heat in both ...

This paper discusses the thermal response of two prototypical International Thermonuclear Experimental Reactor (ITER) divertor channels during simulated loss-of-flow-accident (LOFA) experiments. The thermal response was characterized by the time-to-burnout (TBO), which is a figure of merit on the mockups' survivability. Data from the ...

This paper discusses the thermal response of two prototypical International Thermonuclear Experimental Reactor (ITER) divertor channels during simulated loss-of-flow-accident (LOFA) experiments. The thermal response was characterized by the time-to-burnout (TBO), which is a figure of merit on the mockups' survivability. Data from the ...

A hybrid fusion-fission reactor for the transmutation of spent nuclear fuel is being developed at Georgia Tech. The Subcritical Advanced Burner Reactor (SABR) is a 3000 MWth sodium-cooled, metal TRU-Zr fueled fast reactor driven by a tokamak fusion neutron source based on ITER physics and technology. We are investigating the accident dynamics of SABR's coupled fission, fusion ...

A transient natural convection model of the APT blanket primary heat removal (HR) system was developed to demonstrate that the blanket could be cooled for a sufficient period of time for long term cooling to be established following a loss-of-flow accident (LOFA). The particular case of interest in this report is a complete loss-of-pumping ...

Transient thermal and stress analyses have been conducted with the following three off-normal conditions for the shielding blanket and first wall (FW) structure of International Thermonuclear Experimental Reactor (ITER). (1) Loss of Flow Accident (LOFA) (...

... Descriptors : (*AUSTRALIA, ACCIDENTS), (*ACCIDENTS, STATISTICAL ANALYSIS), MOTOR VEHICLE ACCIDENTS, INDUSTRIAL MEDICINE ...

The paper discusses progress in the system design of the Tiber-II tokamak. In particular, topics discussed are neutronics analysis; thermal hydraulics analysis; activation analysis; LOCA and LOFA analysis; D/He-3 operation on Tiber-II; and a scoping design study of a D/He Tandem mirror reactor. ...

Accident models play a critical role in accident investigation and analysis. Most traditional models

BackgroundFriedreich's ataxia (FRDA) is the most common hereditary ataxia among caucasians. The molecular defect in FRDA is the trinucleotide GAA expansion in the first intron of the FXN gene, which encodes frataxin. No studies have yet reported frataxin protein and mRNA levels in a large cohort of FRDA patients, carriers and controls.Methodology/Principal FindingsWe enrolled 24 patients with ...