A Study of a Nuclear Hydrogen Production Demonstration Plant

Chang, Jonghwa; Kim, Yong‐Wan; Lee, Ki-Young; Lee, Young-Woo; Lee, Won Jae; Noh, Jae Man; Kim, Min-Hwan; Lim, Hong-Sik; Shin, Youngjoon; Bae, Ki Kwang; Jung, Kwang‐Deog

doi:10.5516/net.2007.39.2.111

Cited by 113 publications

(23 citation statements)

References 9 publications

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“…Jepang menargetkan kopling HTTR dengan proses termokimia siklus iodinesulfur dapat terwujud pada akhir dasawarsa 2010 [6,7] . Sementara Korea Selatan yang juga mengadopsi proses ini pada awal 2000-an, menargetkan operasi skala demonstration plant pada tahun 2026 [8] .…”

Section: Pendahuluanunclassified

HTGR Kogenerasi Produksi Hidrogen Untuk Konversi Co2 Menjadi Metanol

Salimy

Alimah²

2016

Jurnal Pengembangan Energi Nuklir

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Section: Pendahuluanunclassified

HTGR Kogenerasi Produksi Hidrogen Untuk Konversi Co2 Menjadi Metanol

Salimy

Alimah²

2016

Jurnal Pengembangan Energi Nuklir

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“…KAERI (Korea Atomic Energy Research Institute) has been developing the NHDD (Nuclear Hydrogen Development and Demonstration) plant which has a capacity of 200MW (thermal) and core outlet temperature of 950qC [3]. A core outlet temperature as high as 950qC is needed for efficient production of hydrogen.…”

Section: Introductionmentioning

confidence: 99%

Preliminary application of the draft code case for alloy 617 for a high temperature component

Lee

Song

2008

J Mech Sci Technol

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The ASME draft Code Case for Alloy 617 was developed in the late 1980s for the design of very-high-temperature gas cooled reactors. The draft Code Case was patterned after the ASME Code Section III Subsection NH and was intended to cover Ni-Cr-Co-Mo Alloy 617 to 982qC (1800qF). But the draft Code Case is still in an incomplete status, lacking necessary material properties and design data. In this study, a preliminary evaluation on the creep-fatigue damage for a high temperature hot duct pipe structure has been carried out according to the draft Code Case. The evaluation procedures and results according to the draft Code Case for Alloy 617 material were compared with those of the ASME Subsection NH and RCC-MR for Alloy 800H material. It was shown that many data including material properties, fatigue and creep data should be supplemented for the draft Code Case. However, when the evaluation results on the creep-fatigue damage according to the draft Code Case, ASME-NH and RCC-MR were compared based on the preliminary evaluation, it was shown that the Alloy 617 results from the draft Code Case tended to be more resistant to the creep damage while less resistant to the fatigue damage than those from the ASME-NH and RCC-MR.

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“…The prismatic core of interest is PMR200 developed at KAERI (Chang et al, 2007). The core consists of 66 fuel element columns.…”

Section: Unit-cell Computational Domainmentioning

confidence: 99%

Study on Influence of Turbulence Model Selection on Prediction of Flow Distribution and Hot Spot Fuel Temperature in Prismatic HTGR Cores

Kim

Tak

Noh

2014

Engineering Applications of Computational Fluid Mechanics

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CFD analyses were performed for a cross-flow experiment in prismatic HTGR core fuel blocks to investigate the effect of turbulence models on the prediction of the core flow distribution. A transition model was considered in addition to a fully turbulent model because the flow in the coolant channels of the fuel block is turbulent whereas that in the bypass gap between the blocks is laminar. Additional analyses were carried out to investigate how the variation of the coolant channel flow dependence on the turbulence model selection affected the hot spot fuel temperature. The results showed that the gamma-theta transition model led to a better prediction than the others because it reasonably simulated the flow region where the bypass and cross gaps intersected. The result for the hot spot fuel temperature, however, showed that the temperature change caused by the turbulence model selection is so small that it can be absorbed in a margin of the engineering design. Therefore, the fully turbulent model can be used as an efficient alternative to the transition model in the engineering calculation of an HTGR core flow.

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A Study of a Nuclear Hydrogen Production Demonstration Plant

Cited by 113 publications

References 9 publications

HTGR Kogenerasi Produksi Hidrogen Untuk Konversi Co2 Menjadi Metanol

HTGR Kogenerasi Produksi Hidrogen Untuk Konversi Co2 Menjadi Metanol

Preliminary application of the draft code case for alloy 617 for a high temperature component

Study on Influence of Turbulence Model Selection on Prediction of Flow Distribution and Hot Spot Fuel Temperature in Prismatic HTGR Cores

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