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The Method of Specific Heat Capacity Measurement for Irradiated Zr-4 Alloy Capsule Material

[+] Author Affiliations
Liang Chen, Hua Pang, Xiaoming Song, Lili Liu, Wenjie Li, Changbing Tang

Nuclear Power Institute of China, Chengdu, China

Paper No. ICONE24-60141, pp. V001T03A008; 3 pages
doi:10.1115/ICONE24-60141
From:
  • 2016 24th International Conference on Nuclear Engineering
  • Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors
  • Charlotte, North Carolina, USA, June 26–30, 2016
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5001-5
  • Copyright © 2016 by ASME

abstract

Specific heat capacity of irradiated and un-irradiated Zr-4 alloy in the temperature range from 40°C to 500°C was measured by DSC (Differential Scanning Calorimetry) in Hot Cell of NPIC for the first time in China. The irradiated discal specimen was sampled from Zr-4 alloy plate, and the dose was about 18μSv/h. The measurement was proceeded on DSC device (404 F1 type), and the data of specific heat capacity was obtained by relative method made use of Proteus analytical software. Discharge air exhausted to hot cell by vent in DSC. The test result indicated that the test method was confirmed feasible and appropriate, then provided an effective approach for thermal parameter measurement for irradiated specimens.

Copyright © 2016 by ASME

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