Design and safety consideration in the High-Temperature engineering Test Reactor (HTTR)

Saito, Shuji; Tanaka, Toŝhiyuki; Sudo, Yukio; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru

doi:10.1016/0360-5442(91)90124-5

Cited by 36 publications

(45 citation statements)

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“…The other optical surveys performed in the southern sky are the Puppis region (230 Saito et al (1991) on the right hand side of our survey (dashed line in Fig. 1), the Ophiuchus Supercluster Region by Wakamatsu et al (1994) and its extension (Wakamatsu et al, in preparation) as well as the Sagittarius region below the Galactic Center (−7 Roman & Saito (1997) and the Aquila/Sagittarius survey (8 Roman et al (1996) on the lefthand side of Fig.…”

Section: ) ∼ (320mentioning

confidence: 65%

A catalog of galaxies behind the Southern Milky Way

Kraan-Korteweg

2000

Astron. Astrophys. Suppl. Ser.

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Section: ) ∼ (320mentioning

confidence: 65%

A catalog of galaxies behind the Southern Milky Way

Kraan-Korteweg

2000

Astron. Astrophys. Suppl. Ser.

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“…(12) to (16), the mass balances under the equilibrium state can be calculated using the flow rate and the equilibrium constants of reactions (7), (8) and (9), i.e., K 1 , K 2 and K 3 , respectively. The equilibrium constant of reaction (7), K 1 , can be expressed by the following equation: 22) log K 1 ¼ 0:292 log T þ ð336:5=TÞ À 1:055: ð17Þ…”

Section: Features and Basic Equationmentioning

confidence: 99%

“…6,7) JAEA has constructed Japan's first HTGR, the high-temperature engineering test reactor (HTTR), with a thermal output of 30 MW and an outlet coolant temperature of 950 C. 8,9) JAEA also has been developing a thermochemical water-splitting iodine-sulfur (IS) process, which can produce hydrogen from water at a temperature lower than 1000 C. 10,11) Since connecting the IS process to the HTGR can produce a large amount of hydrogen without CO 2 emission, this system is a promising candidate for CO 2 -free energy production. The HTTR-IS system 12) is planned as a coupling of the IS process with the HTTR in order to demonstrate hydrogen production with the HTGR and to obtain technical and capital cost data for such future commercial plants as the GTHTR-300C.…”

Section: Introductionmentioning

confidence: 99%

Numerical Study on Tritium Behavior by Using Isotope Exchange Reactions in Thermochemical Water-Splitting Iodine–Sulfur Process

Ohashi

Sakaba

Nishihara

et al. 2007

J. Nucl. Sci. Technol.

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One potential problem in the hydrogen production system coupled with the high-temperature gascooled reactor (HTGR) is transmission of tritium from the primary coolant to the product hydrogen by permeation through the heat transfer tubes. Tritium accumulation in the process chemicals in the components of a hydrogen plant, a thermochemical water-splitting iodine-sulfur (IS) process, will also be a critical issue in seeking to license the hydrogen plant as a non-nuclear plant in the future. A numerical analysis model for tritium behavior in the IS process was developed by considering the isotope exchange reactions between tritium and the hydrogen-containing process chemicals, i.e., H 2 O, H 2 SO 4 and HI. The tritium activity concentration in the IS process coupled with the high-temperature engineering test reactor (HTTR), the HTTR-IS system, was preliminarily evaluated in regard to the effects of some indeterminate parameters, i.e., equilibrium constants of the isotope exchange reactions, permeability of tritium through heat transfer tubes, tritium and hydrogen concentrations in the secondary helium coolant, and the leak rate from the secondary coolant loop. The results describing how the tritium activity concentration changes with variations in these parameters and which component has the maximum tritium activity concentration in the IS process are described in this paper.

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“…From this point of view, the basic design criteria for the fuel are to minimize the failure fraction of coating layers, i.e., as-fabricated failure in production process and significant additional failure during operation. 3) In parallel with the fabrication of the first-loading fuel, integrity confirmation tests of the fuel were carried out by Japan Atomic Energy Research Institute (JAERI). They were (1) as-fabricated SiC failure fraction measurement, (2) hightemperature heatup test of irradiated fuel compact and (3) irradiation test of as-fabricated fuel.…”

Section: )mentioning

confidence: 99%

Integrity Confirmation Tests and Post-irradiation Test Plan of the HTTR First-Loading Fuel

Sawa¹,

Sumita²,

Ueta³

et al. 2001

Journal of Nuclear Science and Technology

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Since the first-loading fuel of the High Temperature Engineering Test Reactor (HTTR) is the first mass-production High Temperature Gas-cooled Reactor (HTGR) fuel in Japan, their quality should be carefully inspected. For the quality control related to the fabrication process, Japan Atomic Energy Research Institute (JAERI) carried out the tests to certify the fuel integrity during operation. The tests comprise (1) as-fabricated SiC failure fraction measurement, (2) high-temperature heatup test of irradiated fuel and (3) accelerated irradiation test. For (1), the SiC failure fraction was measured independently in JAERI in addition to the measurement in the fabrication process. The measured failure fractions agreed within 95% confidence limit. In order to confirm the integrity of the SiC layer with respect to the 1,600• C criterion, the high-temperature heatup test of irradiated fuel compact was carried out. The result showed that no failed particle was present in the fuel compact after heating. The diffusion coefficient of metallic fission products in SiC layer was also examined in a series of post-irradiation heating tests. The measured diffusion coefficient of 137 Cs showed a good holding ability as those obtained for research and development fuel specimen. The measured fission gas release rate in accelerated irradiation test showed no additional failure up to 60 GWd/t which was about two times higher than 33 GWd/t of the maximum burnup in the HTTR core. Through the tests, integrity of as-fabricated first-loading fuel of the HTTR was finally confirmed. The future post-irradiation test plan, which will be carried out to confirm the fuel irradiation performance and to obtain the data on its irradiation characteristics in the core, is also described.

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Design and safety consideration in the High-Temperature engineering Test Reactor (HTTR)

Cited by 36 publications

References 0 publications

A catalog of galaxies behind the Southern Milky Way

A catalog of galaxies behind the Southern Milky Way

Numerical Study on Tritium Behavior by Using Isotope Exchange Reactions in Thermochemical Water-Splitting Iodine–Sulfur Process

Integrity Confirmation Tests and Post-irradiation Test Plan of the HTTR First-Loading Fuel

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