Evaluation of Radionuclides in Concrete Shielding for Nuclear Power Plant Decommissioning-Reference-Cited by-同舟云学术

Evaluation of Radionuclides in Concrete Shielding for Nuclear Power Plant Decommissioning

Published:2009-11 Issue:2 Volume:168 Page:508-512
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Chen Yen-Fu¹,Lin Yen-Kung¹,Sheu Rong-Jiun²,Jiang Shiang-Huei³

Affiliation:

1. National Tsing Hua University Department of Engineering and System Science, 101, Sec. 2, Kung Fu Road Hsinchu 30013, Taiwan

2. National Synchrotron Radiation Research Center 101 Hsin-Ann Road, Hsinchu Science Park, Hsinchu 300, Taiwan

3. National Tsing Hua University Department of Engineering and System Science and Institute of Nuclear Engineering and Science, 101, Sec. 2, Kung Fu Road Hsinchu 30013, Taiwan

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT09-A9234

Reference7 articles.

1. Determination of Long-Lived Neutron Activation Products in Reactor Shielding Concrete Samples

2. Long-lived activation products in TRIGA Mark II research reactor concrete shield: calculation and experiment

3. Activation analysis of concrete and graphite in the experimental reactor RUS

4. J. C. EVANS, E. L. LEPEL, R. W. SANDERS, C. L. WILKERSON, W. SILKER, C. W. THOMAS, K. H. ABEL, and D. R. ROBERTSON, “Long-Lived Activation Products in Reactor Materials,” NUREG/CR-3474, Pacific Northwest Laboratory (1984).

5. I. C. GAULD, O. W. HERMANN, and R. M. WESTFALL, “ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms,” ORNL/TM-2005/39, Version 5.1, Vol. II, Book 1, Sec. F7, Oak Ridge National Laboratory (2006).

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