Power calibration of the TRIGA mark I nuclear research reactor

TRIGA Mark-II Research Reactor

The present work gives a methodology for assessing radiological concentration of I, I, I, I, and I due to a hypothetical accident of TRIGA Mark-II research Reactor at AERE, Savar, Bangladesh. The concentrations were estimated through different pathways like ingestion of vegetation, milk, and meat from air and ground deposition. The maximum air concentrations for all 16 directions were found at ...

Thermoluminescence Dosimetry at the Vienna Triga Mark-ii Research Reactor

Accident scenarios of the TRIGA Mark II reactor in Vienna

The safety report of the TRIGAMark II reactor in Vienna includes three accident scenarios and their deterministic dose consequences to the environment. The destruction of the cladding of the most activated fuel element, the destruction of all fuel elements and a plane crash were considered scenarios in that report. The calculations were made in 1978 with the software program named STRISK. In th...

Serpent-2 Reactor Model Validation at the Vienna Triga Mark Ii Reactor

The Vienna TRIGA Mark II reactor was modelled by means of the Serpent-2 Monte Carlo burnup calculation code. The purpose of the modelling is the determination of core critical parameters and of nuclear fuel composition time evolution. This paper presents the Serpent-2 reactor model validation process carried out during the last year. Taking into account the irradiation history, the fuel composi...

Dose Distribution of 131 I , 132 I , 133 I , 134 I , and 135 I Due to a Hypothetical Accident of TRIGA Mark - II Research Reactor

An attempt has been made in the work to assess radiological dose due to the deposition of 131 I, 132 I, 133 I, 134 I, and 135 I on ground, vegetation, milk and meat considering a hypothetical accident of TRIGA Mark-II research reactor at AERE, Savar, Bangladesh. Contribution of dose from ingestion of vegetation due to 131 I has been found to be dominant (62.96%). Also found that contribution of...