Abstract Molybdenum-99 (99 Mo) is a parent radioisotope of Technetium-99m (99m Tc)
widely used in nuclear diagnostics. The production of this radioisotope by PT. INUKI …

Interrogation of nuclear fuel and Plutonium (Pu) and Uranium (U) discrimination was
performed using Missouri University of Science and Technology Reactor (MSTR) fuel by non …

Uncertainty analysis is performed to qualify the uncertainty of the infinite multiplication factor
(k inf) and nuclide number density induced by cross sections, fission yields and decay half …

Burnup measurement is an important step in material control and accountancy at nuclear
reactors and may be done by examining gamma spectra of fuel samples. Traditional …

In this study, burn-up values​​ of spent fuels were determined using Non-Destructive
Analysis (NDA) with the help of 137 Cs burn-up indicator. Four spent fuel elements (F30 …

This paper investigates how concentrations of certain fission products and their related
gamma-ray emissions can be used to discriminate between uranium oxide (UOX) and mixed …

We present a concise equation correlating the burnup of spent nuclear fuel (SF) with the
neutron count rate, developed through comprehensive data analysis from Origen-ARP and …

ABSTRAK KARAKTERISASI LIMBAH DARI PRODUKSI RADIOISOTOP MOLIBDENUM-99.
Radioisotop 99Mo diproduksi terutama sebagai radioisotop induk untuk memperoleh …

In addition to verifying operator declared parameters of spent nuclear fuel, the ability to
experimentally infer such parameters with a minimum of intrusiveness is of great interest and …

Pebble Bed Reactors are fueled with fuel pebbles that are circulated multiple times through
the reactor vessel before discharge. During the normal operation of a PBR, ejected pebbles …