Challenges in the development of high temperature reactors

Sabharwall, Piyush; Bragg-Sitton, Shannon M.; Stoots, C. M.

doi:10.1016/j.enconman.2013.02.021

Cited by 35 publications

(14 citation statements)

References 6 publications

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“…It is a helium-cooled, graphite-moderated, thermal neutron spectrum reactor with core outlet temperatures greater than 900°C [1]. It has a significant improvement on the fuel utilization, efficiency, safety compared to the light water reactors (LWRs), and enables a new suite of non-electric industrial process heat applications [2]. On the one hand, the high temperature enables a high thermal efficiency for electricity generation.…”

Section: Introductionmentioning

confidence: 99%

Study on local thermal–hydraulic performance and optimization of zigzag-type printed circuit heat exchanger at high temperature

et al. 2015

Energy Conversion and Management

166

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Section: Introductionmentioning

confidence: 99%

Study on local thermal–hydraulic performance and optimization of zigzag-type printed circuit heat exchanger at high temperature

et al. 2015

Energy Conversion and Management

166

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“…Then, the repetitive structure is spread all over the plane (Figure 2(b)). This model (in this paper called Model I) has two major approaches: (1) to consider that the CFPs are uniformly arranged inside the pebble, which ignores the real randomness of the CFPs location, and (2) not to include in the geometry the fraction of CFPs intersected with the pebble's surface, causing the considered fuel mass in the pebble to be less than the real one.…”

Section: Models For the Simulation Of The Triso Particles Inside The mentioning

confidence: 99%

“…The Deviated benchmark was chosen for this study because in 1 The first row of results was obtained with a VSOP bidimensional model and the second with a tridimensional VSOP model. 2 The first row of results was obtained with DELIGHT code and the second with SRAC code.…”

Section: Density Variations In the Dummy Pebblesmentioning

confidence: 99%

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Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

Rosales

Muñoz

Garcı́a

et al. 2014

International Journal of Nuclear Energy

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Very high temperature reactor (VHTR) designs offer promising performance characteristics; they can provide sustainable energy, improved proliferation resistance, inherent safety, and high temperature heat supply. These designs also promise operation to high burnup and large margins to fuel failure with excellent fission product retention via the TRISO fuel design. The pebble bed reactor (PBR) is a design of gas cooled high temperature reactor, candidate for Generation IV of Nuclear Energy Systems. This paper describes the features of a detailed geometric computational model for PBR whole core analysis using the MCNPX code. The validation of the model was carried out using the HTR-10 benchmark. Results were compared with experimental data and calculations of other authors. In addition, sensitivity analysis of several parameters that could have influenced the results and the accuracy of model was made.

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“…RDE belongs to the generation-IV reactor, which is a category for advance reactor and expected to be a solution to some remaining concerns of conventional power reactor regarding the sustainability, economic viability, safety, reliability, and proliferation resistance [2]. RDE is a very attractive solution to the electiricity and heat demand in Indonesia [3].…”

Section: Introductionmentioning

confidence: 99%

Radionuclide Characteristics of Rde Spent Fuels

Husnayani

Udiyani

2018

Tri Dasa Mega

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RADIONUCLIDE CHARACTERISTICS OF RDE SPENT FUELS. Reaktor Daya Eksperimental(RDE) is a 10 MWth pebble-bed High Temperature Gas-cooled Reactor that is planned to be constructed by National Nuclear Energy Agency of Indonesia (BATAN) in Puspiptek complex, Tangerang Selatan. RDE utilizes low enriched UO 2 fuel coated by TRISO layers and loaded into the core by means of multipass loading scheme. Determination of radionuclide characteristics of RDE spent fuel; such as activity, thermal power, neutron and photon release rates; are very important because those characteristics are crucial to be used as a base for evaluating the safety of spent fuel handling system and storage tank. This study is aimed to investigate the radionuclide characteristics of RDE spent fuel at the end of cycle and during the first 5 years cooling time in spent fuel storage. The method used to investigate the radionuclide characteristics is burnup calculation using ORIGEN2.1 code. In performing the ORIGEN2.1 calculation, one pebble fuel was assumed to be irradiated in the core for 5 cycles and then decayed for 5 years. At the end of the fifth cycle, it is obtained that the total activity, thermal power, neutron production, and photon release rates from all radionuclides inside one spent fuel are approximately 105.68 curies, 0.41 watts, 2.65 x 10 3 neutrons/second, and 1.79 x 10 4 photons/second, respectively. The results for the radionuclides characteristics during the first 5 years cooling time in the spent fuel storage show that the radioactivity characteristics from all radionuclides are rapidly decreasing at the first year and then slowly decreasing at the second until the fifth year of cooling time. The results obtained in this study can provide data for safety evaluation of fuel handling and spent fuel storage, such as the calculation of sourceterm, radiation dose rate, and the determination of radiation shielding.Keywords: RDE, spent fuel, radionuclide activity, thermal power, neutron production, photon releaserates ABSTRAK KARAKTERISTIK RADIONUKLIDA DI DALAM BAHAN BAKAR RDE. Reaktor Daya Eksperimental (RDE) adalah reaktor tipe Reaktor Temperatur Tinggi Berpendingin Gas dengan daya termal 10MW yang akan dibangun oleh BadanTenagaNuklirNasional (BATAN) di kawasanPuspiptek, Tangerang Selatan. RDE menggunakan bahan bakar UO 2 yang dilapisi dengan lapisan TRISO dan dimasukkan ke dalam teras RDE menurut skema multipass (5 siklus

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Challenges in the development of high temperature reactors

Cited by 35 publications

References 6 publications

Study on local thermal–hydraulic performance and optimization of zigzag-type printed circuit heat exchanger at high temperature

Study on local thermal–hydraulic performance and optimization of zigzag-type printed circuit heat exchanger at high temperature

Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

Radionuclide Characteristics of Rde Spent Fuels

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