Measurement of the neutron flux distribution in a research reactor by neutron activation analysis

被引:0
|
作者
Park, Byung-Gun [1 ]
Jun, Byung Jin [1 ]
Kang, Gi-Doo [1 ]
Kim, Myong-Seop [1 ]
Yoo, Han Jong [1 ]
Chung, Byun-Young [1 ]
Lee, Byungchul [1 ]
机构
[1] Korea Atom Energy Res Inst, Daedeok Daero 989-111, Daejeon 34057, South Korea
关键词
Neutron flux; Neutron activation analysis; Research reactor; Wire scanning; HPGe detector; Jordan research and training reactor;
D O I
10.1007/s10967-021-07837-2
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
The neutron flux distribution in the core region of the JRTR was measured through the neutron activation analysis method. Sample mount and a tool for withdrawing the sample mount were devised to irradiate the Au wires and foils. The measured data were compared with calculated values to confirm the reliability of the power distribution calculation. The reactor power during irradiation was estimated to be 9% lower than indications of power monitoring systems calibrated at around 10 mu W. The measured transversal and axial neutron reaction rate distributions showed agreement within 1.32% difference with the calculated results.
引用
收藏
页码:501 / 512
页数:12
相关论文
共 50 条
  • [41] Measurement of neutron flux and beam divergence at the cold neutron guide system of the new Munich research reactor FRM-II
    Zeitelhack, K
    Schanzer, C
    Kastenmüller, A
    Röhrmoser, A
    Daniel, C
    Franke, J
    Gutsmiedl, E
    Kudryashov, V
    Maier, D
    Päthe, D
    Petry, W
    Schöffel, T
    Schreckenbach, K
    Urban, A
    Wildgruber, U
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2006, 560 (02): : 444 - 453
  • [42] IN-CORE NEUTRON-FLUX DISTRIBUTION MEASUREMENT BY A CIRCULATING FLUID ACTIVATION METHOD
    FUJII, M
    NUCLEAR SCIENCE AND ENGINEERING, 1973, 50 (03) : 302 - 306
  • [43] Measurement of 14 MeV Neutron Flux from D-T Neutron Generator Using Activation Analysis
    Jakhar, Shrichand
    Rao, C. V. S.
    Shyam, A.
    Das, B.
    2008 IEEE NUCLEAR SCIENCE SYMPOSIUM AND MEDICAL IMAGING CONFERENCE (2008 NSS/MIC), VOLS 1-9, 2009, : 1610 - +
  • [44] A MEASUREMENT OF THE NEUTRON ENERGY DISTRIBUTION IN THE ORNL GRAPHITE REACTOR
    TRICE, JB
    PHYSICAL REVIEW, 1953, 91 (01): : 224 - 224
  • [45] ERRORS OF NEUTRON-ACTIVATION ANALYSIS CONNECTED WITH MONITORING NEUTRON-FLUX IN A NEUTRON GENERATOR
    LISOVSKI.IP
    SMAKHTIN, LA
    ZHURNAL ANALITICHESKOI KHIMII, 1973, 28 (02): : 231 - 234
  • [46] Neutron flux optimization in irradiation channels at NUR research reactor
    Meftah, B.
    Zidi, T.
    Bousbia-Salah, A.
    ANNALS OF NUCLEAR ENERGY, 2006, 33 (14-15) : 1164 - 1175
  • [47] NEUTRON-FLUX CONTROL OF A RESEARCH REACTOR BY A MICROCOMPUTER SYSTEM
    NINAUS, W
    KAHR, G
    ACTA PHYSICA AUSTRIACA, 1980, 52 (3-4): : 331 - 337
  • [48] Determination of fast neutron flux distribution in irradiation sites of the Malaysian Nuclear Agency research reactor
    Yavar, A. R.
    Sarmani, S. B.
    Wood, A. K.
    Fadzil, S. M.
    Radir, M. H.
    Khoo, K. S.
    APPLIED RADIATION AND ISOTOPES, 2011, 69 (05) : 762 - 767
  • [49] Neutron flux distribution and conversion ratio of Critical Experiment Device for molten salt reactor research
    Liu, Yafen
    Yan, Rui
    Zou, Yang
    Kang, Xuzhong
    Zhou, Bo
    Yu, Shihe
    ANNALS OF NUCLEAR ENERGY, 2019, 133 : 707 - 717
  • [50] Experimental determination and simulation of neutron and gamma flux parameters in horizontal channel for Prompt Gamma Neutron activation analysis implementation at Es-Salam research reactor
    Hamidatou, L.
    Slamene, H.
    Dbacha, B.
    Ait-ziane, M.
    Badreddine, A.
    Benaskeur, N.
    Benkharfia, H.
    Alliti, M.
    Attari, K.
    Hachouf, M.
    Djebli, K.
    Lounis-Mokrani, Z.
    APPLIED RADIATION AND ISOTOPES, 2021, 174