Validation of the Pressurized Water Reactor Core Analysis System SEANAP-86 with Measurements in Tests and Operation-Reference-Cited by-同舟云学术

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Validation of the Pressurized Water Reactor Core Analysis System SEANAP-86 with Measurements in Tests and Operation

Published:1988-11 Issue:3 Volume:100 Page:305-313
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Ahnert C.¹,Aragonés J. M.²,Crespo A.²,Labay A.³,León J. R.⁴,Alvarez A. I.²

Affiliation:

1. Junta de Energía Nuclear (JEN-CIEMAT), Madrid, Spain

2. Instituto de Fusión Nuclear (DENIM), Universidad Politécnica de Madrid José G. Abascal, 2, 28006 Madrid, Spain

3. Asociación Nuclear de Ascó (FECSA-ANA II), Barcelona, Spain

4. Central Nuclear de Almaraz (CNA), Madrid, Spain

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE88-A29044

Reference7 articles.

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

2. Physical properties of nodular cast iron for shipping containers and safety analysis by fracture mechanics

3. Core-State Models for Fuel Management of Equilibrium and Transition Cycles in Pressurized Water Reactors

4. D. D. LANNING et al. “GAPCON-THERMAL-3 Code Description,” PNL-2434, Pacific Northwest Laboratory (1978).

Cited by 3 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. Core design: Review & perspectives in Spain;Nuclear Engineering and Design;2024-03

2. Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference;Annals of Nuclear Energy;2016-09

3. Methods and Performance of the Three-Dimensional Pressurized Water Reactor Core Dynamics SIMTRAN On-Line Code;Nuclear Science and Engineering;1996-09

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