Principle design and data of graphite components

Ishihara, Masahiro; Sumita, Junya; Shibata, Taiju; Iyoku, Tatsuo; Oku, Tatsuo

doi:10.1016/j.nucengdes.2004.08.012

Cited by 48 publications

(27 citation statements)

References 4 publications

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“…Bahan bakar yang digunakan adalah jenis prismatik [19,20]. Gas pengotor yang terjadi pada pendingin primer adalah O 2 , N 2 , H 2 O, CH 4 , CO, CO 2 , dan H 2 [18].…”

Section: Sph Httr-jepangunclassified

Kajian Sistem Pemurnian Helium Reaktor HTGR Berdaya Kecil

Alimah¹,

Sriyono

2017

Jurnal Pengembangan Energi Nuklir

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KAJIAN SISTEM PEMURNIAN HELIUM REAKTOR HTGR BERDAYA KECIL.Sistem pemurnian helium (SPH) adalah salah satu sistem keselamatan pada reaktor HTGR. SPH berfungsi membersihkan pengotor yang ada pada pendingin primer, sehingga dampak terhadap struktur, sistem dan komponen (SSK) reaktor minimal. Ada dua jenis pengotor pada pendingin yaitu berbentuk partikulat (debu karbon, produk fisi (Kr, Xe, Cs,dll.)) dan gas (O2, N2, H2O, CH4, CO, CO2, dan H2). Setiap reaktor mempunyai batasan pengotor yang berbeda selama operasi normal tergantung pada daya reaktor, sistem konversi energi dan jenis bahan bakar yang digunakan. Makalah ini membahas SPH pada HTR-10, HTTR dan desain konseptual RDE. Tujuan kajian adalah mengetahui desain SPH yang optimum dan dapat digunakan sebagai masukan desain SPH RDE. Metodologi yang digunakan adalah kajian literatur berdasarkan pengalaman operasi HTR-10 dan HTTR serta evaluasi desain konseptual RDE. Parameter kajian ditekankan pada batasan pengotor yang dipersyaratkan pada operasi normal, komponen utama alat pemurnian, laju alir masa dan proses regenerasi. Komponen utama peralatan pemurnian yang digunakan pada SPH HTR-10, HTTR dan RDE adalah sama yaitu filter, kolom CuO, water cooler, kolom molecular sieve dan karbon aktif kondisi kriogenik. Berdasarkan pengalaman operasi HTR-10 dan HTTR, desain SPH yang digunakan cukup handal dalam menjaga kemurnian pendingin primer, meskipun batasan pengotor yang ditetapkan berbeda. SPH pada HTTR Jepang memiliki penetapan batas yang lebih ketat yaitu tidak boleh ada pengotor N2, CH4 dan O2 pada operasi normal, serta menggunakan precharcoal trap untuk mengadsorpsi debu halus dibawah 0,1 mikron. Kedua parameter ini dapat diadopsi pada desain SPH RDE agar dampak pengotor terhadap SSK minimal. ABSTRACT THE ASSESSMENT OF HELIUM PURIFICATION SYSTEM OF SMALL POWER HTGR.The helium purification system (HPS) is one of safety system of High Temperature Gas-cooled Reactor. HPS removes impurities in the primary coolant, so that the impact on structure, system and component (SSC) is minimized. The two impurity types are particulates (carbon dust, fission products (Kr, Xe, Cs etc.) and the gases (O2, N2, H2O, CH4, CO, CO2, and H2). Every reactor has a different impurity limit during normal operation, depends on the reactor power, energy conversion system and fuel type. This paper discusses the HPS on HTR-10, HTTR and Indonesian RDE conceptual design. The purpose of this assessment is to determine the optimum HPS design as a role model for Indonesian RDE. The utilized methodology is a literature study based on the operating experiences of both HTR-10 and HTTR as well as the evaluation of RDE conceptual design. This study focuses on the impurities limit during normal operation, the main components of HPS, mass flow-rate and regeneration process. The main component that used in HPS for HTR-10, HTTR and RDE are similar i.e. filter, CuO column, water cooler, molecular sieve bed and cryogenic activated carbon bed. Refer to the HTR-10 and HTTR operational experiences, both of those rea...

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“…Bahan bakar yang digunakan adalah jenis prismatik [19,20]. Gas pengotor yang terjadi pada pendingin primer adalah O 2 , N 2 , H 2 O, CH 4 , CO, CO 2 , dan H 2 [18].…”

Section: Sph Httr-jepangunclassified

Kajian Sistem Pemurnian Helium Reaktor HTGR Berdaya Kecil

Alimah¹,

Sriyono

2017

Jurnal Pengembangan Energi Nuklir

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“…The GTMHR's core was assumed to be made of IG-110, a high-strength, fine-grained graphite with isotropic mechanical properties (Ishihara et al 2004). Thermo mechanical properties of the IG-110 in its normal state are shown in Table 4-4.…”

Section: Properties In Standard Conditionsmentioning

confidence: 99%

“…Thermo mechanical properties of the IG-110 in its normal state are shown in Table 4-4. Because the ultimate strengths exhibit statistical variations, the minimum compressive and tensile strengths were determined from statistical treatment of the strength data such that it can be said with 95% confidence that 99% of the graphite samples survive beyond the specified values (Ishihara et al 2004). …”

Section: Properties In Standard Conditionsmentioning

confidence: 99%

“…Ishihara et al (2004) performed mechanical tests on IG-110 samples that were irradiated up to neutron fluence of 3.8u10 22 n/cm 2 (neutron energy >0.05 MeV) at a temperature of 600°C, resulting in neutron dose of ~25 dpa (Burchell et al 1996). 20 n/cm 2 per year (neutron energy > 0.1 MeV) with a neutron dose of 0.56 dpa per year .…”

Section: Young's Modulus and Mechanical Strengths Vs Irradiationmentioning

confidence: 99%

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FINAL REPORT on Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents

Oh¹,

Kim²,

No³

et al. 2011

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(NGNP)/Generation IV very high temperature reactor (VHTR). Phenomena Identification and Ranking studies to date have identified the air ingress event, following on the heels of a VHTR depressurization, as being very important. Consequently, the development of advanced air ingress-related models and verification and validation are a very high priority for the NGNP Project.Following a loss of coolant and system depressurization incident, air ingress will occur through the break, leading to oxidation of the in-core graphite structure and fuel. This study indicates that depending on the location and the size of the pipe break, the air ingress phenomena are different. In an effort to estimate the proper safety margin, experimental data and tools, including accurate multidimensional thermal-hydraulic and reactor physics models, a burn-off model and a fracture model are required. It will also eventually require effective strategies to mitigate the effects of oxidation.This 3-year project (FY 2008 to FY 2010 focused on various issues related to the VHTR air-ingress accident, including (a) analytical and experimental study of air ingress caused by density-driven, stratified, countercurrent flow, (b) advanced graphite oxidation experiments, (c) experimental study of burn-off in the core bottom structures, (d) structural tests of the oxidized core bottom structures, (e) implementation of advanced models developed during the previous tasks into the GAMMA code, (f) full air ingress and oxidation mitigation analyses, (g) development of core neutronic models, (h) coupling of the core neutronic and thermal hydraulic models, and (i) verification and validation of the coupled models. E-1. RESEARCH OBJECTIVESThe main objectives of this 3-year project were to investigate air-ingress related phenomena in the VHTRs and perform modeling and experiments for better understanding on the accident consequences. The major phenomena, targeted in this study, were (1) density gradient driven stratified flow, (2) graphite oxidation and structural degradation, (3) thermal hydraulics and neutronics coupling, and (4) development of air ingress mitigation and computational fluid dynamics (CFD) calculations E-2. REPORT CONTENT AND ORGANIZATIONThis report, which highlights key accomplishments achieved from FY 2008 to FY 2010, consists of the following sections:1. Introduction: Section 1 is introductory information about this project with objectives and strategies.

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“…In contrast to the excellent thermal and electrical properties, graphite has weak mechanical properties represented by a bending strength that does not exceed 100 MPa. 1) Molds made of graphite do not hence withstand higher sintering pressure. The development of new materials with excellent mechanical as well as thermal and electrical properties are desired.…”

Section: Introductionmentioning

confidence: 99%

Effect of TiN addition on the properties of spark plasma sintered TiB<sub>2</sub>

Koide

Khaled²,

Saito

et al. 2017

J. Ceram. Soc. Japan

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The sintering of hardly sintered TiB 2 powder has been investigated using the spark plasma sintering (SPS) technique. The investigation revealed that TiB 2 powder can be sintered to highly dense bulk samples using SPS technique. However optimization of the sintering condition could not generate bulk samples with a fine microstructure. The addition of TiN was found to be effective in obtaining bulk samples with fine structure. Sample bending strength largely improved from 120 MPa for TiN free samples to more than 373 MPa, much higher than that of graphite, for TiN containing samples. The improvement in bending strength is attributed to the fine structure formed and to the strong bonding between TiB 2 and TiN particles.

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Principle design and data of graphite components

Cited by 48 publications

References 4 publications

Kajian Sistem Pemurnian Helium Reaktor HTGR Berdaya Kecil

Kajian Sistem Pemurnian Helium Reaktor HTGR Berdaya Kecil

FINAL REPORT on Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents

Effect of TiN addition on the properties of spark plasma sintered TiB<sub>2</sub>

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