Activation and Radioactive Waste Analysis for Survey X-Ray Crystal Spectrometer of ITER-Reference-Cited by-同舟云学术

Activation and Radioactive Waste Analysis for Survey X-Ray Crystal Spectrometer of ITER

Published:2017-02-14 Issue:2 Volume:71 Page:215-224
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Subhash P. V.¹,Indauliya Gunjan²,Chaitanya T. Sai¹,Kanth Priti¹,Jakhar S.³,Varshney Sanjeev¹,Kumar Siddharth¹,Krishna Raja⁴,Bhaliya Nirav²,Mishra Sapna¹,Shrishail P.¹,Kumar Vinay¹

Affiliation:

1. ITER-India, Institute for Plasma Research, Gandhinagar, Gujarat, India

2. Bhakti Management Services Pvt. Ltd., Gandhinagar, Gujarat, India

3. Institute for Plasma Research, Gandhinagar, Gujarat, India

4. University of Petroleum and Energy Studies (UPES), Dehradun, India

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST16-241

Reference11 articles.

1. LOUGHLIN M. J. et al. “Recommended Plasma Scenarios for Activation Calculations,” ITER IDM ITER_D_2V3V8G, Vol. 1.1, ITER Organization (2009).

2. Bragg x-ray survey spectrometer for ITER

3. Monte Carlo radiation shielding and activation analyses for the Diagnostic Equatorial Port Plug in ITER

4. SHIMADA M. et al. “Heat and Nuclear Load Specification for ITER,” ITER_D_2LULDH, Vol. 2.3, ITER Organization (2010).

Cited by 8 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Development of unstructured mesh tally capability in cosRMC and application to shutdown dose rate analysis;Fusion Engineering and Design;2022-08

2. Estimation of production cross-sections, transmutation and gas generation from radionuclides (A ∼50–60) in fusion environment;Applied Radiation and Isotopes;2022-06

3. Development of shutdown dose rate calculation code based on cosRMC and application to benchmark analysis;Fusion Engineering and Design;2021-12

4. A study on irradiated welding joints in ITER materials and its effects on FMECA analysis of components;Fusion Engineering and Design;2020-09

5. ACTYS-ASG, tool for coupling ACTYS-1-GO with ATTILA;Fusion Engineering and Design;2018-04