INVAP′s Research Reactor Designs

Villarino, Eduardo; Doval, A.

doi:10.1155/2011/490391

Cited by 16 publications

(3 citation statements)

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“…Proposed simulations are developed using different sources, according to McStas virtual and MCNP source components, to investigate the dependence of the initial wavelength profile. In this first approach, we define some cases with guides and distances based on OPAL thermal guides, i.e., Bunker guides with length of 40 , section area of 30 × 5 2 and final position (of Echidna) about 15 from the Bunker exit. These cases, however, are just a simplified configuration for the RMB guide system and a complete study for its proper definition is let for future work.…”

Section: Introductionmentioning

confidence: 99%

“…In 2010, an international committee of a bilateral agreement between Brazil and Argentina, namely COBEN (Bi-national Commission on Nuclear Energy), decided to adopt the conceptual model of the Australian research reactor OPAL as a base for the new reactor projects of both countries [1]. The OPAL was designed and built by the Argentinian technological company INVAP [2], which is also responsible for the project of the new Brazilian Multipurpose Reactor (RMB). In these terms, the RMB possesses the Australian reactor as a reference for radioisotope production and instruments that use neutron beams.…”

Section: Introductionmentioning

confidence: 99%

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Neutron Guide Building instruments of the Brazilian Multipurpose Reactor (RMB) project

Souza¹,

Oliveira²,

Yokaichiya³

et al. 2020

J. Inst.

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A growing community of scientists has been using neutrons in the most diverse areas of science. In order to meet the researchers demand in the areas of physics, chemistry, materials sciences, engineering, cultural heritage, biology and earth sciences, the Brazilian Multipurpose Reactor (RMB) will provide 3 thermal guides and 3 cold guides, with the installation of several instruments for materials characterization. In this study, we present a standard design requirement of two primordial instruments, namely Sabiá and Araponga. They are, respectively, cold and thermal neutron instruments and correspond to a Small-Angle Neutron Scattering (SANS) and High-Resolution Powder Neutron Diffractometer (HRPND) to be installed in the Neutron Guide Building (N02) of RMB. To provide adequate flux for both instruments, we propose here an initial investigation of the use of simple and split guides to transport neutron beams to two different instruments on the same guide. For this purpose, we use Monte Carlo simulations utilizing McStas software to check the efficiency of thermal neutron transport for different basic configuration and sources. By considering these results, it is possible to conclude that the split guide configuration is, in most cases, more efficient than cases that use transmitted neutron beams independently of source. We also verify that the employment of different coating indexes for concave and convex surfaces on curved guides is crucial, at least on simulated cases, to optimise neutron flux (intensity and divergence) and diminish facility installation cost. References 21As a multipurpose reactor, the RMB project also contains applications in neutron research and instruments. The neutron applications of the RMB project are the irradiation process, which occurs inside the reflector tank, and measurement process, which takes place at the N02 building (number 14 in Figure 1) and is often complementary to synchrotron radiation investigations. According to the basic project, there will be available in-core positions for materials irradiation tests and positions inside reflector for applying the neutron activation analysis (NAA) technique, which possesses numerous applications, e.g., in geology, archaeology, biology, medicine, environment, industry, chemistry, nutrition, and agriculture.Concerning applications inside N02, the detailed project of RMB contains, according to the main current research reactors, a series of state-of-art instruments that still have to be properly defined. In this study, we present two priority neutron scattering instruments that compose the detailed project of the RMB neutron guide hall (N02), namely Small-Angle Neutron Scattering (SANS) and the High-Resolution Powder Neutron Diffractometer (HRPND).SANS is a flexible and disseminated technique for studying object structures on the nanoscale. Besides its unique property in investigating magnetic material, not contemplated by traditional SAXS technique (Small Angle X-Ray Scattering). SANS is used in looking to polymer and biological molec...

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Neutron Guide Building instruments of the Brazilian Multipurpose Reactor (RMB) project

Souza¹,

Oliveira²,

Yokaichiya³

et al. 2020

J. Inst.

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show abstract

“…e plate-type fuel with the uranium density of 3 gU/cm 3 was also used in the MPRR design with the power of 20 MW for achieving high neutron fluxes at irradiation channels [5]. Several designs of MPRRs include the OPAL reactor (20 MW) in Australia [9,10], the CARR reactor (60 MW) in China, the RA-10 reactor (30 MW) in Argentina [11], the HFIR reactor (85 MW) in USA, the FRM-II reactor (20 MW) in Germany [12], the HANARO reactor (30 MW) in Korea [13,14], JRR-3M (20 MW) in Japan, the RMB reactor (30 MW) in Brazil [15], and the JRTR reactor (5 MW) in Jordan [16]. A comparison among several MPRRs shows that the FRM-II reactor achieves the highest thermal flux per unit power with a maximum thermal neutron flux of 8 × 10 14 n•cm −2 •s −1 [6].…”

Section: Introductionmentioning

confidence: 99%

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

Nguyen

Huynh

et al. 2020

Science and Technology of Nuclear Installations

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The paper presents a conceptual design of a 10 MW multipurpose nuclear research reactor (MPRR) loaded with the low-enriched uranium (LEU) VVR-KN fuel type. Neutronics and burnup calculations have been performed using the REBUS-MCNP6 linkage system code and the ENDF/B-VII.0 data library. The core consists of 36 fuel assemblies: 27 standard fuel assemblies and 9 control fuel assemblies with the uranium density of 2.8 gU/cm3 and the 235U enrichment of 19.75 wt.%. The cycle length of the core is 86 effective full-power days with the excess reactivity of 9600 and 1039 pcm at the beginning of cycle and the end of cycle, respectively. The highest power rate and the highest discharged burnup of fuel assembly are 393.49 kW and 56.74% loss of 235U, respectively. Thermal hydraulics analysis has also been conducted using the PLTEMP4.2 code for evaluating the safety parameters at a steady state of the hottest channel. The maximum temperatures of coolant and fuel cladding are 66.0°C and 83.0°C, respectively. This value is lower than the design limit of 98°C for cladding temperature. Thermal fluxes at the vertical irradiation channels and the horizontal beam ports have been evaluated. The maximum thermal fluxes of 2.5 × 1014 and 8.9 ×1013 n·cm−2·s−1 are found at the neutron trap and the beryllium reflector, respectively.

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Neutronic design investigation of a liquid injection-based second shutdown system for a typical research reactor using MCNPX

Boustani

Hassanzadeh

2018

NUCL SCI TECH

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INVAP′s Research Reactor Designs

Cited by 16 publications

References 0 publications

Neutron Guide Building instruments of the Brazilian Multipurpose Reactor (RMB) project

Neutron Guide Building instruments of the Brazilian Multipurpose Reactor (RMB) project

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

Neutronic design investigation of a liquid injection-based second shutdown system for a typical research reactor using MCNPX

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