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

来源：

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2021年 / 330卷 / 02期

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

页码：501 / 512

页数：12

共 13 条

[1] [Anonymous], 2001, Report of the Advisory Group on Tax Policy and Tax Administration for the Tenth Plan
[2] Assessment of the Implementation of a Neutron Measurement System During the Commissioning of the Jordan Research and Training Reactor
Bae, Sanghoon
Suh, Sangmun
Cha, Hanju
[J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (03) : 504 - 516
[3] Measurement and simulation of the neutron flux distribution in the TRIGA Mark II reactor core
Chiesa, Davide
Clemenza, Massimiliano
Nastasi, Massimiliano
Pozzi, Stefano
Previtali, Ezio
Scionti, Giuseppe
Sisti, Monica
Prata, Michele
Salvini, Andrea
Cammi, Antonio
[J]. ANNALS OF NUCLEAR ENERGY, 2015, 85 : 925 - 936
[4] Comparison of first criticality prediction and experiment of the Jordan research and training reactor (JRTR)
Kim, Kyung-O
Jun, Byung Jin
Lee, Byungchul
Park, Sang-Jun
Roh, Gyuhong
[J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (01) : 14 - 18
[5] Methods for Processing ENDF/B-VII with NJOY
MacFarlane, R. E.
Kahler, A. C.
[J]. NUCLEAR DATA SHEETS, 2010, 111 (12) : 2739 - 2889
[6] Universal curve of the thermal neutron self-shielding factor in foils, wires, spheres and cylinders
Martinho, E
Salgado, J
Gonçalves, IF
[J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2004, 261 (03) : 637 - 643
[7] Energy distribution of the neutron flux measurements at the Chilean Reactor RECH-1 using multi-foil neutron activation and the Expectation Maximization unfolding algorithm
Molina, F.
Aguilera, P.
Romero-Barrientos, J.
Arellano, H. F.
Agramunt, J.
Medel, J.
Morales, J. R.
Zambra, M.
[J]. APPLIED RADIATION AND ISOTOPES, 2017, 129 : 28 - 34
[8] National Nuclear Data Center Brookhaven National Laboratory, NUDAT2 8
[9] Neutron fluence measurements, 1970, TECHN REP SER INT AT, V107
[10] Measurement of kinetic parameter of the Jordan research and training reactor
Park, Beomwoo
Jun, Byung Jin
Yoo, Hanjong
Lee, Byungchul
Park, Sang-Jun
Roh, Gyuhong
Khafaji, Salih
[J]. ANNALS OF NUCLEAR ENERGY, 2019, 132 : 322 - 326

← 1 2 →