Conceptual Design Station Blackout and Loss-of-Flow Accident Analyses for the Advanced Neutron Source Reactor-Reference-Cited by-同舟云学术

Conceptual Design Station Blackout and Loss-of-Flow Accident Analyses for the Advanced Neutron Source Reactor

Published:1994-04 Issue:1 Volume:106 Page:31-45
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Fletcher C. D.¹,Ghan L. S.¹,Determan J. C.¹,Nielsen H. H.¹

Affiliation:

1. Idaho National Engineering Laboratory, EG&G Idaho, Inc., P.O. Box 1625 Idaho Falls, Idaho 83415-3885

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/NT94-A34948

Reference15 articles.

1. Reactor Design of the Advanced Neutron Source

2. Thermal-Hydraulic Systems Safety Analysis to Support the Design Process for the Advanced Neutron Source Reactor

3. K. E. CARLSON, R. A. RIEMKE, S. Z. ROUHANI, R. W. SHUMWAY, and W. L. WEAVER, “RELAPS/M0D3 Code Manual, Volume I: Code Structure, System Models, and Solution Methods,” NUREG/CR-5S3S, EGG-2S96, Idaho National Engineering Laboratory (June 1990).

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