Destructive Gamma-Ray Analysis of Fuel Rods from the Taiwan Research Reactor

Author:

Pan Lung-Kwang1

Affiliation:

1. Chung Cheng Institute of Technology Department of Mechanical Engineering, Tahsi, 33500, Taoyuan, Taiwan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference20 articles.

1. P. S. SONG, H. L. LEE, and D. I. LEE, “The Development and Use of a Travelling In-Core Flux Detector for TRR Reactor,” INER-T1091, Institute of Nuclear Energy Research (1986).

2. C. S. TSAO, T. T. YANG, and T. LEE, “Nondestructive Burnup Determination of TRR Testing Fuel Rods FR-01 and SI by Cs-137 Counting Rate and Cs-134/Cs-137 Activity Ratio from Gamma Spectroscopy,” INER-T1251, Institute of Nuclear Energy Research (1987).

3. Profiles of Activity Ratios of Fission Products, Cesium-134, Cesium-137 and Ruthenium-106 in Low-Enriched PUO2-UO2Fuel Assemblies

4. Non-Destructive Gamma-Ray Spectrometry on Spent Fuels of a Boiling Water Reactor

5. S. T. HSUE and T. W. CRAN, “Non-Destructive Assay Methods for Irradiated Nuclear Fuels,” LA-6923, Los Alamos National Laboratory (1978).

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