A Neutronic Evaluation of Reprocess Fuel and Depletion Study of VHTR Using MCNPX and WIMSD5 Code-Reference-Cited by-同舟云学术

A Neutronic Evaluation of Reprocess Fuel and Depletion Study of VHTR Using MCNPX and WIMSD5 Code

Published:2012-01 Issue:1T Volume:61 Page:338-342
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Cardoso F.¹,Pereira C.¹,Veloso M. A. F.¹,Silva C. A. M.¹,Cunha R.¹,Costa A. L.¹

Affiliation:

1. Departamento de Engenharia Nuclear, Universidade Federal de Minas Gerais, Belo Horizonte, MG Brazil Instituto Nacional de Ciências e Tecnologia de Reatores Inovadores/CNPq fabinuclear@yahoo.com.br; claubia@nuclear.ufmg.br

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/FST12-A13442

Reference11 articles.

1. Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with tru-fueled VHTR

2. “Used fuel” vectors and waste minimization strategies for VHTRS operating without refueling

3. D. WARIN, Future nuclear fuel cycles: prospect and challenges for actinide recycling, Materials Science and Engineering 9 012063, doi:10.1088/1757-899X/9/1/012063(2010)

4. Long-Cycle and High-Burnup Fuel Assembly for the VHTR

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