The Effect of Time Delays in Fuel Pin Failure on LOF-TOP Transient Calculations for a Commercial-Sized LMFBR
Author:
Affiliation:
1. Argonne National Laboratory, 9700 S. Cass Ave., Argonne, Illinois 60439
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/NT82-A32860
Reference7 articles.
1. H. H. HUMMEL, P. A. PIZZICA, and KALLIMULLAH, “Studies of Unprotected Loss-of-Flow Accidents for the Clinch River Breeder Reactor,” ANL-76-51, Argonne National Laboratory (Apr. 1976).
2. H. H. HUMMEL KALLIMULLAH, and P. A. PIZZICA, “Physics and Pump Coastdown Calculations for a Model of a 4000 MWe Oxide-Fueled LMFBR,” ANL-76-77, Argonne National Laboratory (June 1976).
3. J. F. MEYER et al. “An Analysis and Evaluation of the Clinch River Breeder Reactor Core Disruptive Accident Energetics,” NUREG-0122, NRR/USNRC, U.S. Nuclear Regulatory Commission (Mar. 1977).
4. A Numerical Model of Reactor Fuel and Coolant Motions Following Pin Failure
5. P. A. PIZZICA, P. L. GARNER, and P. B. ABRAMSON, “A Users Guide to EPIC, A Computer Program to Calculate the Motion of Fuel and Coolant Subsequent to Pin Failure in an LMFBR,” ANL-80-47, Argonne National Laboratory (May 1980).
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