Fuel element burnup determination in mixed TRIGA core using reactor calculations

被引：0
|
作者：
Institute Jožef Stefan, Jamova 39, 1000 Ljubljana, Slovenia [1 ]
机构：
来源：
Nucl Technol | / 1卷 / 35-45期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
相关论文
共 50 条
  • [21] PERFORMANCE TESTING OF A MIXED CORE UTILIZING TRIGA-STANDARD AND TRIGA-FLIP FUEL
    RANDALL, JD
    FELTZ, DE
    GODSEY, T
    HARDT, M
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 : 16 - 16
  • [22] DETERMINATION OF CORE BURNUP ISOTOPIC INVENTORY AND CONVERSION RATIO FROM SELECTIVE SAMPLING OF SPENT REACTOR FUEL
    JEDRUCH, J
    NODVIK, RJ
    NUCLEAR APPLICATIONS, 1967, 3 (08): : 507 - &
  • [23] GAMMA-SPECTROMETRIC BURNUP DETERMINATION IN REACTOR FUEL RODS
    HILLER, S
    KERNTECHNIK, 1970, 12 (11) : 485 - &
  • [24] Nondestructive experimental measurement of fuel element burnup in Xi'an pulse reactor
    Northwest Institute of Nuclear Technology, Xi'an 710024, China
    Hedongli Gongcheng, 2009, 3 (30-34): : 30 - 34
  • [25] JS']JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations
    Pungercic, Anse
    Haghighat, Alireza
    Snoj, Luka
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (08) : 3405 - 3424
  • [26] Determination of the breakage of reactor fuel element by using the Cerenkov counting
    Tsinghua Univ, Beijing, China
    Hedongli Gongcheng/Nuclear Power Engineering, 1996, 17 (03): : 213 - 217
  • [27] Fuel loading, criticality and control rod worth calculations of the Triga Mark III reactor using Serpent and MCNP
    Hernandez-Galeana J.
    Galicia-Aragon J.
    Gomez-Torres A.
    Filio-López C.
    International Journal of Nuclear Energy Science and Technology, 2019, 13 (01) : 38 - 60
  • [28] DESTRUCTIVE BURNUP DETERMINATION OF REACTOR-FUEL ELEMENTS - METHODS AND TRENDS
    HERMANN, A
    KERNENERGIE, 1973, 16 (12): : 362 - 369
  • [29] Comparative Analysis of Preliminary Design Core of TRIGA Bandung Using Fuel Element Plate MTR in Indonesia
    Ramadhan, Anwar Ilmar
    Umar, Efrizon
    Tandian, Nathanael Panagung
    Suwono, Aryadi
    ADVANCING NUCLEAR SCIENCE AND ENGINEERING FOR SUSTAINABLE NUCLEAR ENERGY KNOWLEDGE, 2017, 1799
  • [30] Burnup Credit Evaluation for BWR Spent Fuel from Full Core Calculations
    Detkina, Anna
    Litskevitch, Dzianis
    Peakman, Aiden
    Merk, Bruno
    APPLIED SCIENCES-BASEL, 2020, 10 (21): : 1 - 19
12345