Calculation of the temperature in the container unit with a modified design for the production of 99 Mo at the VVR-Ts re
- PDF / 494,943 Bytes
- 9 Pages / 612 x 792 pts (letter) Page_size
- 13 Downloads / 150 Views
RATION AND APPLICATION OF ISOTOPES. MASS SPECTROMETRY
Calculation of the Temperature in the Container Unit with a Modified Design for the Production of 99Mo at the VVRTs Research Reactor Facility (IVV.10M) A. A. Kazantseva,*, V. V. Sergeevb, and O. Yu. Kochnovc a
Experimental Scientific Research and Methodology Center Simulation Systems, Obninsk, Kaluga oblast, 249035 Russia b c
Leipunsky Institute of Physics and Power Engineering, Obninsk, Kaluga oblast, 249033 Russia
Karpov Institute of Physical Chemistry (Obninsk Branch), Obninsk, Kaluga oblast, 249020 Russia *email: [email protected] Received February 19, 2014
Abstract—The temperature regime is calculated for two different designs of containers with uraniumbearing material for the upgraded VVRTs research reactor facility (IVV.10M). The containers are to be used in the production of 99Mo. It is demonstrated that the modification of the container design leads to a considerable temperature reduction and an increase in the nearwall boiling margin and allows one to raise the amount of material loaded into the container. The calculations were conducted using the international thermohydraulic contour code TRAC intended to analyze the technical safety of watercooled nuclear power units. Keywords: upgraded VVRTs (IVV.10M), thermophysical modeling, nuclear power station safety, TRAC code, 99Mo production. DOI: 10.1134/S1063778815120145
INTRODUCTION The use of radionuclides in medicine has now become so widespread in the world that the people sur veyed associate nuclear materials with medical appli cations (and not with nuclear reactors and power engi neering) in roughly half the instances. It is a vital task to reach this worldwide level, which is common to the western world and the Muslim world, in Russia. The production of technetium generators in Obninsk is planned to be expanded. The 99Mo radionuclide (raw material for technetium generators) will be produced at a VVRTs reactor. Backup production of 99Mo com menced at the Scientific Research Institute of Atomic Reactors (Dimitrovgrad) in 2010. During scheduled preventive maintenance, 99Mo will be transported from Dimitrovgrad to Obninsk for processing. When uraniumbearing material is irradiated in a reactor, molybdenum (raw material for the production of tech netium) is obtained. The resulting product is used in the diagnostics of oncological diseases at the early stages (when it is easier to localize and cure them); in the diag nostics of thyroid, heart, liver, and kidney diseases; and in tomography. Therefore, 99Mo is the most widely used medical radionuclide with halflife T = 66 h. The project aimed at establishing a network of “active” beds throughout Russia starting from 2015 is
now in the works. Less than 50 such beds are available at present, while the required number is 40 times higher (more than 2000 beds are needed). The pro duction site should not be far from active beds, and the production should be running continuously (the half life of technetium is shorter than 6 h). The
Data Loading...
