Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5

Abstract

Neutronics analysis has been performed for the 500 kW Dalat Nuclear Research Reactor loaded with highly enriched uranium fuel using the SRAC code system. The effective multiplication factors, keff, were analyzed for the core at criticality conditions and in two cases corresponding to the complete withdrawal and the full insertion of control rods. MCNP5 calculations were also conducted and compared to that obtained with the SRAC code. The results show that the difference of the keff values between the codes is within 55 pcm. Compared to the criticality conditions established in the experiments, the maximum differences of the keff values obtained from the SRAC and MCNP5 calculations are 119 pcm and 64 pcm, respectively. The radial and axial power peaking factors are 1.334 and 1.710, respectively, in the case of no control rod insertion. At the criticality condition these values become 1.445 and 1.832 when the control rods are partially inserted. Compared to MCNP5 calculations, the deviation of the relative power densities is less than 4% at the fuel bundles in the middle of the core, while the maximum deviation is about 7% appearing at some peripheral bundles. This agreement indicates the verification of the analysis models.

Conceptual Design of a 10 MW Multipurpose Research Reactor Using VVR-KN Fuel

“…In the case of emergency shutdown, the control rods fall into the core by the gravity. e safety and shim rods use B 4 C as a neutron absorbing material with the density of 1.69 g/cm 3 . e AR rod is made of stainless steel with the density of 7.8 g/cm 3 for a smaller reactivity worth.…”

“…e core is loaded with Russian VVR-M2 fuel. e operation of the DNRR is mainly for radioisotope production (RI), neutron activation analysis (NAA), basic and applied researches, and training [3,4]. However, due to the limitation of power and experimental facilities, the DNRR cannot meet the increasing demands of radioisotope production for medical and industrial applications, facilities for nuclear physics experiments, and support to nuclear power development in the future.…”

“…e IRT-1 reactor in Libya is the only one using tube-type fuel. In the last 30 years, the MTR fuel with the density of 4.8 gU/cm 3 and burnable poison integrated fuel elements was mostly used in the designs of high-performance MPRRs. e KJRR reactor in Korea is designed using the MTR fuel with a high density of 8.0 gU/cm 3 and beryllium and graphite reflectors [8].…”

“…Neutronics and burnup calculations have been performed using the REBUS-MCNP6 linkage system code. e VVR-KN fuel assembly contains low enriched uranium fuel with the density of 2.8 gU/cm 3 . e active core is surrounded by a beryllium reflector to attain high thermal neutron fluxes and high performance of irradiation channels.…”

Steady-State Thermal-Hydraulic Analysis of the LEU-Fueled Dalat Nuclear Research Reactor

“…In the first phase, the reactor core was partially converted in September 2007 to a mixed core of 98 irradiated HEU and 6 fresh LEU VVR-M2 FBs, and in the second phase, the reactor with an entire LEU core of 92 FBs was commissioned and put into operation in early 2012. At present, the reactor is operated continuously for about 150 hrs at full power, once every 1 or 2 weeks, for radioisotope production, neutron activation analysis, basic and applied researches, and education and training [2,3].…”