Fuel Management and Core Design Code Systems for Pressurized Water Reactor Neutronic Calculations-Reference-Cited by-同舟云学术

Fuel Management and Core Design Code Systems for Pressurized Water Reactor Neutronic Calculations

Published:1985-06 Issue:3 Volume:69 Page:350-367
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Ahnert Carol¹,Aragonés José M.²

Affiliation:

1. Junta de Energia Nuclear, División de Reactores Avda. Complutense, 22; 28040 Madrid, Spain

2. Universidad Politecnica de Madrid Departamento Energía Nuclear; ETS-Industriales Po. Castellana, 80; 28046 Madrid, Spain

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/NT85-A33617

Reference13 articles.

1. C. ANHERT and J. M. ARAGONES, “MARIA System: A Code Block for PWR Fuel Assembly Calculations,” JEN-543, Junta de Energía Nuclear (1983).

2. M. J. HALSALL, “A Summary of WIMS-D4 Input,” AEEW-M-1327, U.K. Atomic Energy Establishment, Winfrith (1980).

3. Criticality Calculations for Uniform Water-Moderated Lattices

4. F. J. FAYERS et al. “LWR-WIMS, A Modular Computer Code for the Evaluation of Light Water Reactors. Description of Methods,” AEEW-R-785, U.K. Atomic Energy Establishment, Winfrith (1972).

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