Long time experience with the development of HTR fuel elements in Germany

Nickel, H.; Nabielek, H.; Pott, G.; Mehner, A.-W.

doi:10.1016/s0029-5493(02)00128-0

Cited by 100 publications

(39 citation statements)

References 8 publications

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“…In this concept evaluation we have not done a complete 3-D analysis of the thermal-hydraulic of our core, that will require a 3-D computational fluid dynamic (CFD) modelling of a basic pattern of the core and a 2-D porous media analysis, to get a detailed temperature mapping of the fuel and the coolant. Nevertheless, we believe that safety operation of this pebble bed core is taken for granted as similar studies with higher outlet Helium temperature (1273 K, +50 °C in comparison to our design) (Nickel et al, 2002;Maki et al, 2007;Tálamo et al, 2004) reported fuel temperatures below 1600 K, maximum allowed in this fuel type, even under accidental conditions. The Kugeler-Schulten correlation has been selected for the pressure drop estimation in the porous model of the core.…”

Section: Thermal-hydraulicssupporting

confidence: 58%

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Abánades

Garcı́a

García

et al. 2011

Nuclear Engineering and Design

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simultaneous transmutation and hydrogen generation based on a graphite-gas configuration already described in (Abánades and Pérez-Navarro, 2007). Section 2 shows the hydrogen generation and transmutation scheme of the proposed pebble bed device. Section 3 introduces the computational tools used for the neutronic calculations of the device core, benchmarking them with previous existing codes, and the results obtained with those tools. Some radiological discussions regarding our proposal are developed in Section 4. Section 5 analyses the thermal-hydraulics behavior of the device. Finally, in Section 6, these results are used for our concept of the performance of the installation for hydrogen production. Conceptual design of the proposed nuclear based Hydrogen generation scheme

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Section: Thermal-hydraulicssupporting

confidence: 58%

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Abánades

Garcı́a

García

et al. 2011

Nuclear Engineering and Design

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“…It uses TRISO particles (Nickel et al, 2002) as fuels. In addition to the aforementioned advantages, VHTR with TRISO fuels can burn Pu-239 very effectively (Greenspan et al, 2006).…”

Section: Very High Temperature Reactormentioning

confidence: 99%

Roles and effects of pyroprocessing for spent nuclear fuel management in South Korea

Ahn

2014

Progress in Nuclear Energy

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Republic of Korea (ROK) changed its spent nuclear fuel policy from the once-through usage and direct disposal to a total system approach that includes pyroprocessing, sodium-cooled fast reactors, and a twotier geological repository to achieve a breakthrough for domestic deadlock situation and thus enable sustainable utilization of nuclear power, but caused disagreement in the bilateral negotiation with the United States (US) for the Nuclear Cooperation Agreement. Analysis has revealed that this shift is effective to make a breakthrough for domestic deadlock because it augments variety of technological options, with which more reversible decision-making process can be conducted to accommodate broad public needs. A trade-off has been explored first by deriving four engineering options from the ROK's system concept and then by comparing their performance from six viewpoints. The option including separation of high-heat emitting radionuclides by the electrolytic reduction process has been recommended.This option should be modified as exogenous and endogenous situations change in future. It is imperative for ROK to integrate a public-participatory decision-making process that works in concert with technology development. US can verify that ROK's motivation is not deviating from successful spent fuel management by checking if a transparent process with public participation is conducted.

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“…The newly invigorated and improved TRISO technology has enabled fuel and reactor designers to extend the application of TRISO particles to other fuel and reactor systems. In conventional hightemperature gas-cooled reactor (HTGR) applications, the TRISO particles are dispersed in a graphitic matrix, producing compacts in the form of pebbles or pellets (Nickel et al, 2002;Phillips et al, 2010). Under the FCM fuel concept, the graphite matrix is replaced with a SiC matrix that offers the following potential advantages: (i) improved irradiation stability Snead et al, 2008), (ii) incorporation of yet another effective barrier to fission product release, (iii) environmental stability under operating (steady state) and transient conditions as well as long-term storage, and (iv) proliferation resistance.…”

Section: Manufacturing Of Fully Ceramic Microencapsulated Fuel Samplementioning

confidence: 99%

Fully Ceramic Microencapsulated (FCM) Replacement Fuel for LWRs

Powers¹,

Lee

Venneri

et al. 2013

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Long time experience with the development of HTR fuel elements in Germany

Cited by 100 publications

References 8 publications

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Roles and effects of pyroprocessing for spent nuclear fuel management in South Korea

Fully Ceramic Microencapsulated (FCM) Replacement Fuel for LWRs

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