scholarly journals Dose Calculation and Measurement from B¹⁰(n, α)Li⁷ Reaction Using Filtered Neutron Beam at Nuclear Research Institute

2021 ◽  
Vol 8 (1) ◽  
pp. 29-35
Author(s):  
Tu Anh Trinh Thi ◽  
Danh Hung Nguyen ◽  
Dang Quyet Pham ◽  
Ngoc Son Pham

In this research, dose calculation and measurement from B10 (n, α) Li7 reaction usingfiltered neutron beam at the Nuclear Research Institute have been reported. Calculation was carried out by Monte Carlo method using MCNP5 code. Neutron activation technique using vanadium foil was employed to determine neutron flux at various positions in phantom from which neutron dose has been calculated using conversion factor. These calculations are basics for the dose determination research of the Boron Neutron Capture Therapy (BNCT) in Vietnam.

Author(s):  
Josef Podlaha ◽  
Karel Svoboda

In 2007, spent nuclear fuel (SNF) from the Nuclear Research Institute Rˇezˇ plc (NRI) was shipped to the Russian Federation for reprocessing. A large amount of SNF of Russian origin has been accumulated after 50 years of research reactor operation. The shipment was realized in the frame of the Russian Research Reactor Fuel Return (RRRFR) program under the US-Russian Global Threat Reduction Initiative (GTRI). SNF shipment from NRI to the Russian Federation represented a very complex and complicated technical, legal and contractual scope of work. The SNF shipment has been realized under specific conditions: 1. High capacity SˇKODA VPVR/M casks were used for transportation for the first time. 2. For the first time, high enriched uranium SNF from a research reactor has been sent to the Russian Federation from a European Union country under the appropriate intergovernmental agreements, legal regulations and conditions. NRI also participates in shipments of SNF from other countries within the framework of the RRRFR program. NRI participated in shipments of SNF from Bulgaria and Hungary in 2008, from Poland in 2009 and 2010, from Ukraine in 2010. Shipments from Belarus and Serbia are planned in 2010. The second shipment of the residue of high enriched SNF from NRI after changeover of the reactor operation to low enriched fuel will be implemented in 2013. The experiences gained during the SNF transportation are described in the paper together with the present and future NRI activities in support of the SNF shipment from other countries.


Author(s):  
Josef Podlaha ◽  
Karel Svoboda ◽  
Eduard Hansli´k

After more than 55 years of activities of the Nuclear Research Institute Rez (NRI) in the nuclear field, there are some obsolete nuclear facilities that shall be decommissioned. NRI is a leading institution in all areas of nuclear R&D in the Czech Republic. NRI has had a dominant position in the nuclear programme since it was established in 1955 as a state-owned research organization and it has developed to its current status. In December 1992, NRI has been transformed into a joint-stock company. The Institute’s activity encompasses nuclear physics, chemistry, nuclear power, experiments at the research reactor and many other topics. Main issues addressed in NRI in the past decades were concentrated on research, development and services provided to the nuclear power plants operating VVER reactors, development of chemical technologies for fuel cycle and irradiation services to research and development in the industrial sector, agriculture, food processing and medicine. The NRI operates two research nuclear reactors, many facilities as a hot cell facility, research laboratories, technology for radioactive waste (RAW) management, radionuclide irradiators, an electron accelerator, etc. The obsolete facilities to be decommissioned comprise various research facilities and facilities for RAW management. Decommissioning of nuclear facilities NRI is the only ongoing decommissioning project in the Czech Republic. Decommissioning started in 2003 and will be finished in 2014. Some facilities have already been successfully decommissioned.


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