REVIEW OF INVESTIGATIONS PERTINENT TO THE PREDICTION OF THE THERMAL BEHAVIOR OF FAST REACTORS UNDER ABNORMAL OPERATING CONDITIONS
Results are summarized for a survey of methods for predicting fuel element and coolant behavior in sodiumcooled fast reactors under abnormal operating conditions. Circumstances prior to, during, and after meltdown are considered, and the behavior of fuel and coolant during transients is discussed. Reactor excursions, theory of fuel element thermal transients, reactor coolant transients in single and two-phase flows, and specific topics such as two-phase flow patterns, two-phase pressure drop, and transient voids in boiling coolant reactors are also treated. Some applicable mathematical treatments are given along with an annotated bibliography. (D.L.C.)
- Research Organization:
- Nuclear Development Associates, Inc., White Plains, N.Y.
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-15-016714
- OSTI ID:
- 4048767
- Report Number(s):
- NDA-2147-4
- Country of Publication:
- United States
- Language:
- English
Similar Records
STUDIES RELATED TO PREDICTING COOLANT BEHAVIOR FOR FAST REACTOR SAFETY
TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR
High Resolution Measurements Reveal Transient Boiling Phenomena under Exponential Heat Inputs
Technical Report
·
Thu Aug 31 00:00:00 EDT 1961
·
OSTI ID:4838436
TRANSIENT BEHAVIOR OF AN ADVANCED SODIUM GRAPHITE REACTOR
Technical Report
·
Thu Nov 30 23:00:00 EST 1961
·
OSTI ID:4823381
High Resolution Measurements Reveal Transient Boiling Phenomena under Exponential Heat Inputs
Journal Article
·
Fri Jul 01 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:23042947