Structural Integrity Assessment of Reactor Assembly Components of a Pool-Type Sodium Fast Reactor in a Core Disruptive Accident—I: Development of Computer Code and Validations-Reference-Cited by-同舟云学术

Structural Integrity Assessment of Reactor Assembly Components of a Pool-Type Sodium Fast Reactor in a Core Disruptive Accident—I: Development of Computer Code and Validations

Published:2010-10 Issue:1 Volume:172 Page:1-15
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Chellapandi P.¹,Chetal S. C.¹,Raj Baldev¹

Affiliation:

1. Indira Gandhi Centre for Atomic Research, Kalpakkam-603 102, 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/NT10-A10878

Reference18 articles.

1. Y. M. CHANG and J. G. VILDYS, “REXCO-HEP, A Two-Dimensional Computer Code for Calculating the Primary System Response in Fast Reactors,” ANL-75-19, Argonne National Laboratory (1975).

2. M. S. COWLER, “ASTARTE—A 2-D Lagrangian Code for Unsteady Compressive Flow Theoretical Description,” AWRE-44-91-37, United Kingdom Atomic Energy Authority (1974).

3. The computer code SEURBNUK-2 for fast reactor containment safety studies

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