Development of HTGR-coated particle fuel technology in Korea

Lee, Young-Woo; Park, Jiyeon; Kim, Yeon Ku; Jeong, Kyung Chae; Kim, Woong Ki; Kim, Bong Goo; Kim, Young Min; Cho, Moon Sung

doi:10.1016/j.nucengdes.2007.11.023

Cited by 24 publications

(15 citation statements)

References 14 publications

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“…However, to obtain SiC with lower density, much higher MTS concentrations were used. Five coating experiments were made by adjusting the MTS concentration via changing the carrier gas flow at 1450 C. The densities of 2.20 g/cm 3 and 2.60 g/cm 3 were obtained under the condition of MTS concentration of 16.0 and 8.0 vol%, respectively. Intermediate densities were obtained by adjusting the MTS concentration.…”

Section: Resultsmentioning

confidence: 99%

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An improved design of TRISO particle with porous SiC inner layer by fluidized bed-chemical vapor deposition

Liu

Chang

et al. 2015

Journal of Nuclear Materials

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Section: Resultsmentioning

confidence: 99%

“…For the structure of the TRISO fuel particle, the inner layer referred as the buffer layer is porous pyrolytic carbon with a density of 0.9 g/cm 3 . The buffer layer can attenuate fission recoils and provide void volume for gaseous fission products as well as carbon monoxide (CO).…”

Section: Introductionmentioning

confidence: 99%

An improved design of TRISO particle with porous SiC inner layer by fluidized bed-chemical vapor deposition

Liu

Chang

et al. 2015

Journal of Nuclear Materials

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“…, COPA (Korea), PARFUME (INL, U.S.), and a fuel performance code developed by the Japan Atomic Energy Research Institute (JAERI). 4,5 Although most of the fuel particle codes have unique capabilities and limitations, PARFUME is recognized for its computational efficiency, closed-form stress/displacement analytical solution method, and dual-solution scheme (i.e., Monte Carlo and numerical integration) for computing failure probability.…”

Section: Fuel Performance Codesmentioning

confidence: 99%

“…The simulation of FP transport via diffusion from the fuel through the particle coating layers to the surrounding fuel element graphite matrix, and finally to the coolant boundary, is accomplished using the following fundamental transport equation of Equation (2)(3)(4), where the flux is driven by FP concentration gradients and temperature gradients as shown in Equation (2)(3)(4)(5).…”

Section: Compute Fission Product Diffusion (Step 5)mentioning

confidence: 99%

PARFUME User's Guide

Hamman¹

2010

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PARFUME, a fuel performance analysis and modeling code, is being developed at Idaho National Laboratory (INL) for evaluating gas-reactor coated particle fuel for prismatic, pebble bed, and plate type fuel geometries. The code is an integrated mechanistic analysis tool that evaluates the thermal, mechanical, and physico-chemical behavior of (tri-isotropic [TRISO]) coated fuel particles and the probability for fuel failure given the particle-to-particle statistical variations in physical dimensions and material properties that arise during the fuel fabrication process. Using a robust finite difference numerical scheme, PARFUME is capable of performing steady-state and transient heat transfer and fission-product diffusion analyses for the fuel. Written in FORTRAN 77, PARFUME compiles in FORTRAN 90 and is easy to read, maintain, and modify. Currently, PARFUME is supported only on Linux platforms.

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“…The result of the measurement determines the disposition of the fuel element, that is, to unload it as spent fuel or return it to the core [6]. If the measured burnup is incorrect, and spent fuel is recycled back into the core, the fuel cladding material can be damaged and increase the risk of radioactive material leakage [7][8][9][10]. In contrast, if the fuel has not yet reached the discharge burnup value, and it is discharged as spent fuel, this leads to increased cost and nuclear fuel waste [11].…”

Section: Introductionmentioning

confidence: 99%

Application of Anticoincidence Technology to Burn-Up Measurement Systems in High-Temperature Gas-Cooled Reactors

2018

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Nuclear energy is the focus of sustainable energy development worldwide. A hightemperature gas-cooled reactor (HTGR) plays a vital role in the development of nuclear energy. In a pebble-bed HTGR, the burn-up measurement system is important for ensuring reactor safety and economy. This study optimized a burn-up measurement system by adding anticoincidence technology with bismuth germanium oxide (BGO) crystals and a plastic scintillator used as anticoincidence detectors. Through Monte Carlo simulation, the detection effects of two different anticoincidence detectors on fuel elements were compared and analyzed. The study focused on varying the wall thickness and top thickness of these detectors to optimize the peak-to-Compton ratio (P/C). The results showed that the size of the BGO detector with the best anticoincidence effect (P/C of 727) consists in a diameter of 140 mm and a length of 210 mm. The best plastic scintillator size (P/C of 180) consists in a diameter of 260 mm and a length of 260 mm. Adding the anticoincidence technology lowered the Compton plateau of the measured gamma spectrum and significantly improved the detection performance of the burn-up measurement system. The new burn-up measurement system has improved detection precision not only for Cs-137 but also for low-activity nuclides.

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Development of HTGR-coated particle fuel technology in Korea

Cited by 24 publications

References 14 publications

An improved design of TRISO particle with porous SiC inner layer by fluidized bed-chemical vapor deposition

An improved design of TRISO particle with porous SiC inner layer by fluidized bed-chemical vapor deposition

PARFUME User's Guide

Application of Anticoincidence Technology to Burn-Up Measurement Systems in High-Temperature Gas-Cooled Reactors

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