Effects of Cooling Fluid Flow Rate on the Critical Heat Flux and Flow Stability in the Plate Fuel Type 2 MW TRIGA Reactor

Rahardjo, Henky Poedjo; Wardhani, Veronica Indriati Sri

doi:10.17146/aij.2017.789

Cited by 3 publications

(2 citation statements)

References 8 publications

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“…(1) While the previous core design has no AT in the CIP design, it was used as a basis to study thermal hydraulics of PTRRB [16][17][18]. Installation of AT for irradiation at CIP will affect coolant flow.…”

Section: Resultsmentioning

confidence: 99%

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Bahrum¹,

Handiaga²,

Setiadi³

et al. 2020

Tri Dasa Mega

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One of the results from Plate Type Research Reactor Bandung (PTRRB) research program is PTRRB core design. Previous study on PTRRB has not calculated neutron flux distribution at its central irradiation position (CIP). Distribution of neutron flux at CIP is of high importance especially in radioisotope production. In this study, CIP was modeled as a stack of four to five aluminum tubes (AT), each filled by four aluminum irradiation capsules (AIC). Considering AIC dimension and geometry, there are three possibilities of AT configuration. For irradiation sample, 1.45 gr of molybdenum (Mo) was put into AIC. Neutron flux distribution at Mo sample was calculated using TRIGA MCNP and MCNP software. The calculation was simulated at condition when fresh fuel is loaded into reactor core. Analyses of excess reactivity show that, after installing irradiation AT and Mo sample was put into each configuration, the excess reactivity is less than 10.9 %. The highest calculated thermal neutron flux at Mo sample is 5.08×1013 n/cm2.s at configuration 1. Meanwhile, the highest total neutron flux at Mo sample is located at capsule no. II and III. Thermal neutron flux profile is the same for all configurations. This result will be used as a basic data for PTRRB utilization.Keywords: Central Irradiation Position, Neutron Flux Distribution, MCNP, PTRRB

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Section: Resultsmentioning

confidence: 99%

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Bahrum¹,

Handiaga²,

Setiadi³

et al. 2020

Tri Dasa Mega

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“…However, its operation depends on the fuel supplied by General Atomics (GA). Since GA no longer produces the TRIGA reactor fuel, and in regard with the production of domestic fuel elements, the replacement of the TRIGA reactor core from fuel cylinder to the fuel plate is planned [2,3].…”

Section: Introductionmentioning

confidence: 99%

Conceptual Design On N16 Decay Chamber For Modified TRIGA-2000 With Plate-Type Fuel

Dibyo¹,

Pinem

Wardhani³

2018

Jurnal Pengembangan Energi Nuklir

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Conceptual Design On N16 Decay Chamber For Modified TRIGA-2000 With Plate-Type Fuel. the TRIGA-2000 is a research reactor in bandung that will be modified using plate-type fuel. The reactor core cooling system is changed from the natural convection cooling mode to the forced convection mode. The purpose of the study is to assess the conceptual design for the decay chamber of N16 nuclide in the primary cooling system of the reactor. In this design, the hold-up system decays the nuclide of N16 resulted from neutron activation product. In the period of 50 seconds, the activity of N16 (T1/2= 7.13 seconds) decays 7 time from half life to low level. The cube shape of decay chamber is provided a plate with 4 hollows and facility to flush the cavitation bubbles. The decay chamber, which is submerged into the bulk shielding as located outside of the reactor pool. The conceptual design uses the Fluent software compared with the analytical estimation for flow velocity in the decay chamber. The result shows a good agreement range with the analytical estimations. The uniform flow profile can be obtained at the velocity of about 0.4 m/s. Water flow life time of 50 seconds in the decay chamber with the capacity of 3.5 m3 is able to decay the N16 nuclide to low level. This decay chamber is expected to contribute in completing the design of reactor primary coolant system using the forced convection mode.

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Design of Irradiation Facilities at Grid E-1 of Plate Type Research Reactor Bandung

Bahrum

Wibowo

Setiadi

et al. 2020

J. Phys.: Conf. Ser.

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Design of Irradiation Facilities at Grid E-1 of Plate Type Research Reactor Bandung. Plate Type Research Reactor Bandung (PTRRB) core design is one of the result of PTRRB research programs. In the previous study the irradiation facilities at grid E-1 has not been designed and also distribution of thermal, epithermal and fast neutron flux at grid E-1 has not been studied. Since that data is very important especially in radioisotope production and neutron beam tube analysis, therefore in this study irradiation facilities at grid E-1will be designed. Previous PTRRB core design is a base for designing irradiation facilities at grid E-1. Considering geometrical of grid E-1 and aluminum tube dimension there are three possibilities aluminum tube configuration. The configurations are configuration 1, 2 and 3. Each configuration was modelled as arrangement of four aluminum tubes and each tube filled by four aluminum irradiation capsules. That configuration was starting point to made MCNP PTRRB reactor core model so there are three MCNP PTRRB reactor core model. MCNP PTRRB reactor core model is needed because MCNP software are computer program for calculating excess reactivity and neutron flux distribution at grid E-1. Result excess reactivity calculation of three configuration indicate that after installing irradiation tube excess reactivity is lower than of limit excess reactivity value 10.9 % of neutronic safety criteria of PTRRB design. Based on neutronic safety criteria, the three configuration is accepted for irradiation facilities PTRRB. Neutron flux calculation result of three configuration reveals that the highest neutron flux is located at capsule no II and III. Profile of thermal neutron flux, epithermal neutron flux and fast neutron flux of three configurations are similar. Neutron flux of thermal, epithermal and fast neutron of three configuration are slightly different. The calculation result reveal that highest thermal neutron flux at grid E-1 is 2.70 × 1013(n/cm 2.sec) at configuration 2. Based on neutronic safety criteria and thermal neutron flux, configuration 2 is appropriate for irradiation facilities of PTRRB.

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Effects of Cooling Fluid Flow Rate on the Critical Heat Flux and Flow Stability in the Plate Fuel Type 2 MW TRIGA Reactor

Cited by 3 publications

References 8 publications

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Design of Irradiation Facilities at Central Irradiation Position of Plate Type Research Reactor Bandung

Conceptual Design On N16 Decay Chamber For Modified TRIGA-2000 With Plate-Type Fuel

Design of Irradiation Facilities at Grid E-1 of Plate Type Research Reactor Bandung

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