Development and Fabrication of 70% PuC–30% UC Fuel for the Fast Breeder Test Reactor in India-Reference-Cited by-同舟云学术

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Development and Fabrication of 70% PuC–30% UC Fuel for the Fast Breeder Test Reactor in India

Published:1986-01 Issue:1 Volume:72 Page:59-69
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Ganguly Chaitanyamoy¹,Hegde Parameshwar Venkappa¹,Jain Gyan Chand¹,Basak Uddharan¹,Mehrotra Radhey Shyam¹,Majumdar Sukomal¹,Roy Pradip Ranjan¹

Affiliation:

1. Bhabha Atomic Research Centre Radiometallurgy Division, Bombay 400 085, India

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/NT86-A33753

Reference21 articles.

1. Uranium-Plutonium Carbide Fuel for Fast Breeder Reactors

Cited by 39 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. Fabrication of Nuclear Fuel Elements;Nuclear Fuel Cycle;2023

2. Separation of Plutonium from Other Actinides and Fission Products in Ionic Liquid Medium;Separation & Purification Reviews;2022-06-09

3. A highly precise micro-analytical XRF method for compositional characterization of fast breeder reactor fuels;Journal of Analytical Atomic Spectrometry;2022

4. Phase Relationships in the Carbon–Titanium–Uranium System for Ultra-High Temperature Nuclear Fuels;JOM;2021-10-01

5. Evaluation and validation of external neutron source strength of operating Fast Breeder Test Reactor;Nuclear Engineering and Design;2021-02

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