BASIC STUDIES ON NEUTRON EMISSION-RATE METHOD FOR BURNUP MEASUREMENT OF SPENT LIGHT-WATER-REACTOR FUEL BUNDLE

被引：7

作者：

UEDA, M ^{[1
]}

KIKUCHI, S ^{[1
]}

KIKUCHI, T ^{[1
]}

KUMANOMIDO, H ^{[1
]}

SEINO, T ^{[1
]}

机构：

[1] TOSHIBA CO LTD, ISOGO ENGN CTR, ISOGO KU, YOKOHAMA 235, JAPAN

来源：

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 1993年 / 30卷 / 01期

关键词：

NEUTRON EMISSION RATES; BURNUP; MEASURING METHODS; LIGHT WATER; SPENT FUEL BUNDLES; FRESH FUEL; EXPERIMENT; U-238; SUBCRITICAL NEUTRON FLUX; NEUTRON COUNT RATES;

D O I：

10.3327/jnst.30.48

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The neutron emission-rate (NER) method for burnup measurement of a spent LWR fuel bundle submerged in water has been studied by focusing on the spatial higher harmonics effects inevitable for the application of a formula based on the one-point reactor model. Verification studies of this method have been made through calculations and simulation experiments using the fresh UO2 fuel-rod bundles of n x n arrays (3 less-than-or-equal-to n less-than-or-equal-to 23, 0.22 less-than-or-equal-to k(eff) less-than-or-equal-to 0.94), and its applicability has been shown for the spent fuel bundle. As a practical example, an actual formula has been given for a spent PWR fuel bundle of 14 x 14 array of 3.5 wt% initial enrichment and cooling time of 1,000 days.

引用

页码：48 / 59

页数：12

共 5 条

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YOKOYAMA, T
TAMURA, T
NUCLEAR TECHNOLOGY, 1982, 57 (03) : 372 - 388
[2] Sensitivity of the neutron multiplication factor to gadolinium isotopes' nuclear data for light water reactor fuel assemblies in the peak reactivity burnup range
Chiba, Go
ANNALS OF NUCLEAR ENERGY, 2021, 151
[3] Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods
Caruso, S.
Jatuff, F.
PROGRESS IN NUCLEAR ENERGY, 2014, 72 : 49 - 54
[4] Calculation of the neutron flux density distribution in two dimensional hexagonal fuel assembly of light water reactor by transmission probability method
Zhang, Y.
Xie, Z.S.
Zhang, J.M.
Deng, L.
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2001, 35 (01): : 1 - 8
[5] The FLEXBURN neutron transport code developed by the S-n method with transmission probabilities in arbitrary square meshes for light water reactor fuel assemblies
Kameyama, T
Matsumura, T
Sasaki, M
NUCLEAR SCIENCE AND ENGINEERING, 1996, 123 (01) : 86 - 95

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