The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material

Liang Chen; Hua Pang; Xiaoming Song; Lili Liu; Wenjie Li; Changbing Tang

doi:10.1115/ICONE24-60141

The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material

Liang Chen
, Hua Pang
, Xiaoming Song
, Lili Liu
, Wenjie Li
, Changbing Tang

Nuclear Power Institute of China

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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.

Original language	English
Title of host publication	Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791850015
DOIs	https://doi.org/10.1115/ICONE24-60141
State	Published - 2016
Externally published	Yes
Event	2016 24th International Conference on Nuclear Engineering, ICONE 2016 - Charlotte, United States Duration: 26 Jun 2016 → 30 Jun 2016

Publication series

Name	International Conference on Nuclear Engineering, Proceedings, ICONE
Volume	1

Conference

Conference	2016 24th International Conference on Nuclear Engineering, ICONE 2016
Country/Territory	United States
City	Charlotte
Period	26/06/16 → 30/06/16

Access to Document

10.1115/ICONE24-60141

Cite this

Chen, L., Pang, H., Song, X., Liu, L., Li, W., & Tang, C. (2016). The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material. In Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors Article V001T03A008 (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 1). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE24-60141

Chen, Liang ; Pang, Hua ; Song, Xiaoming et al. / The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material. Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors. American Society of Mechanical Engineers (ASME), 2016. (International Conference on Nuclear Engineering, Proceedings, ICONE).

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title = "The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material",

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.",

author = "Liang Chen and Hua Pang and Xiaoming Song and Lili Liu and Wenjie Li and Changbing Tang",

note = "Publisher Copyright: Copyright {\textcopyright} 2016 by ASME.; 2016 24th International Conference on Nuclear Engineering, ICONE 2016 ; Conference date: 26-06-2016 Through 30-06-2016",

year = "2016",

doi = "10.1115/ICONE24-60141",

language = "英语",

series = "International Conference on Nuclear Engineering, Proceedings, ICONE",

publisher = "American Society of Mechanical Engineers (ASME)",

booktitle = "Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors",

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Chen, L, Pang, H, Song, X, Liu, L, Li, W & Tang, C 2016, The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material. in Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors., V001T03A008, International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 1, American Society of Mechanical Engineers (ASME), 2016 24th International Conference on Nuclear Engineering, ICONE 2016, Charlotte, United States, 26/06/16. https://doi.org/10.1115/ICONE24-60141

The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material. / Chen, Liang; Pang, Hua; Song, Xiaoming et al.
Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors. American Society of Mechanical Engineers (ASME), 2016. V001T03A008 (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 1).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material

AU - Chen, Liang

AU - Pang, Hua

AU - Song, Xiaoming

AU - Liu, Lili

AU - Li, Wenjie

AU - Tang, Changbing

PY - 2016

Y1 - 2016

N2 - 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.

AB - 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.

UR - https://www.scopus.com/pages/publications/84995743753

U2 - 10.1115/ICONE24-60141

DO - 10.1115/ICONE24-60141

M3 - 会议稿件

AN - SCOPUS:84995743753

T3 - International Conference on Nuclear Engineering, Proceedings, ICONE

BT - Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors

PB - American Society of Mechanical Engineers (ASME)

T2 - 2016 24th International Conference on Nuclear Engineering, ICONE 2016

Y2 - 26 June 2016 through 30 June 2016

ER -

Chen L, Pang H, Song X, Liu L, Li W, Tang C. The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material. In Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors. American Society of Mechanical Engineers (ASME). 2016. V001T03A008. (International Conference on Nuclear Engineering, Proceedings, ICONE). doi: 10.1115/ICONE24-60141

The method of specific heat capacity measurement for irradiated ZR-4 alloy capsule material

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