FILTER FOR THE SELECTIVE REMOVAL OF TRITIUM FROM THE COOLANT GAS OF A HIGH-TEMPERATURE NUCLEAR-REACTOR

被引：2
|
作者：
INIOTAKIS, N
FROHLING, W
VONDERDECKEN, CB
机构：
来源：
JOURNAL OF THE LESS-COMMON METALS | 1983年 / 89卷 / 02期
关键词：
D O I：
10.1016/0022-5088(83)90357-0
中图分类号：
O64 [物理化学（理论化学）、化学物理学];
学科分类号：
070304 ; 081704 ;
摘要：
引用
收藏
页码：465 / 474
页数：10
相关论文
共 50 条
  • [21] A HIGH-TEMPERATURE REACTOR - COAL AND NUCLEAR-ENERGY FOR THE GENERATION OF ELECTRICITY AND GAS
    KELBER, G
    ERDOL & KOHLE ERDGAS PETROCHEMIE, 1988, 41 (04): : 138 - 139
  • [22] Working Mechanism of an Ethanol Filter for Selective High-Temperature Methane Gas Sensors
    Wiesner, Kerstin
    Knoezinger, Helmut
    Fleischer, Maximilian
    Meixner, Hans
    IEEE SENSORS JOURNAL, 2002, 2 (04) : 354 - 359
  • [23] MONTE-CARLO SIMULATION OF THE EMERGENCY SHUTDOWN SYSTEM FOR THE HIGH-TEMPERATURE PEBBLE-BED NUCLEAR-REACTOR
    BIENIASZ, L
    MOSCINSKI, J
    NIZEGORODCEW, P
    RYCERZ, Z
    ANNALS OF NUCLEAR ENERGY, 1983, 10 (06) : 299 - 303
  • [24] EVALUATION OF TRITIUM CONFINEMENT PERFORMANCE OF ALUMINA AND ZIRCONIUM FOR TRITIUM PRODUCTION IN A HIGH-TEMPERATURE GAS-COOLED REACTOR FOR FUSION REACTORS
    Katayama, Kazunari
    Ushida, Hiroki
    Matsuura, Hideaki
    Fukada, Satoshi
    Goto, Minoru
    Nakagawa, Shigeaki
    FUSION SCIENCE AND TECHNOLOGY, 2015, 68 (03) : 662 - 668
  • [25] COMMERCIAL TESTING OF A UNIT FOR HIGH-TEMPERATURE REMOVAL OF CORROSION PRODUCTS FROM WATER COOLANT
    BRAGIN, VB
    KOROSTELEV, DP
    MURAKOV, YB
    NESHKOV, PF
    ORLOV, AK
    PROKHOROV, NA
    TRETYAKOV, SY
    FAMINTSYN, AM
    TSEKH, AR
    SHARYGIN, LM
    SOVIET ATOMIC ENERGY, 1989, 67 (01): : 515 - 522
  • [26] Thermodynamic Analysis of Power Generation Cycles With High-Temperature Gas-Cooled Nuclear Reactor and Additional Coolant Heating Up to 1600 °C
    Dudek, Michal
    Kolenda, Zygmunt
    Jaszczur, Marek
    Stanek, Wojciech
    JOURNAL OF ENERGY RESOURCES TECHNOLOGY-TRANSACTIONS OF THE ASME, 2018, 140 (02):
  • [27] Coolant chemistry of the high temperature gas-cooled reactor 'HTTR'
    Sakaba, Nariaki
    Nakagawa, Shigeaki
    Furusawa, Takayuki
    Emori, Koichi
    Tachibana, Yukio
    Transactions of the Atomic Energy Society of Japan, 2004, 3 (04) : 388 - 395
  • [28] Corrosion of high temperature alloys in the coolant helium of a gas cooled reactor
    Cabet, C
    Monnier, A
    Terlain, A
    HIGH TEMPERATURE CORROSION AND PROTECTION OF MATERIALS 6, PRT 1 AND 2, PROCEEDINGS, 2004, 461-464 : 1165 - 1172
  • [29] A simulation method for nuclear power plant with high-temperature gas-cooled reactor
    Chen, Yang
    You, Jiang-Hong
    Shao, Zhi-Jiang
    Qian, Ji-Xin
    Shi, Xu-Hua
    Gao Xiao Hua Xue Gong Cheng Xue Bao/Journal of Chemical Engineering of Chinese Universities, 2014, 28 (01): : 110 - 114
  • [30] HYDRAULICS OF COOLANT FLOW THROUGH CONTROL ROD CHANNEL IN VERY HIGH-TEMPERATURE GAS-COOLED REACTOR
    OGAWA, M
    AKINO, N
    SHIINA, Y
    FUJIMURA, K
    TAKEDA, T
    EMORI, K
    OHUCHI, M
    KAWAMURA, H
    HISHIDA, M
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1987, 24 (01) : 75 - 83
12345