Activated corrosion products (CRUD) behavior study. Interim report No. 1. Progress during FY 1977
Technical Report
·
OSTI ID:5281502
During FY 1977, a test facility was designed, built, and installed on the N Reactor recirculating primary coolant system to provide representative sampling of suspended and dissolved activated corrosion products in the primary coolant during all modes of reactor operation. Analytical and data acquisition procedures were developed. Preliminary crud transport models were derived for subsequent evaluation with data provided by the sampling system.
- Research Organization:
- United Nuclear Industries, Inc., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01857
- OSTI ID:
- 5281502
- Report Number(s):
- UNI-893; ON: DE84007288
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
N-REACTOR
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PRODUCTION REACTORS
RADIOACTIVITY TRANSPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAMPLING
WATER COOLED REACTORS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
N-REACTOR
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PRODUCTION REACTORS
RADIOACTIVITY TRANSPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAMPLING
WATER COOLED REACTORS