A NUCLEAR-THERMAL ITERATION ANALYSIS OF A BOILING CORE WITH THE ABRAC, BRIC AND CNCR CODES
Technical Report
·
OSTI ID:4729371
A test problem is examined in which the boiling water moderator distribution and power distribution are allowed to interact. The Bettis- developed one-, two-, and threedimensional depletion codes which provide for the moderator variation are used. A comparison of the threedimensional solution and a synthesized three-dimensional solution is made. Conclusions concerning the limitations and possible advantages with each method are drawn. (auth)
- Research Organization:
- Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-17-007574
- OSTI ID:
- 4729371
- Report Number(s):
- WAPD-T-1225
- Country of Publication:
- United States
- Language:
- English
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A NUCLEAR-THERMAL ITERATION ANALYSIS OF A BOILING CORE WITH THE ABRAC, BRIC, AND CNCR CODES
Journal Article
·
Thu Jun 01 00:00:00 EDT 1961
· Trans. Am. Nuclear Soc.
·
OSTI ID:4046060