Fission product behavior in the Peach Bottom and Fort St. Vrain HTGRs
Actual operating data from Peach Bottom and Fort St. Vrain were compared with code predictions to assess the validity of the methods used to predict the behavior of fission products in the primary coolant circuit. For both reactors the measured circuit activities were significantly below design values, and the observations generally verify the codes used for large HTGR design.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- DOE Contract Number:
- AT03-76ET35300
- OSTI ID:
- 7044013
- Report Number(s):
- GA-A-16154; TRN: 81-000852
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PEACH BOTTOM-1 REACTOR
FISSION PRODUCTS
PRIMARY COOLANT CIRCUITS
VRAIN REACTOR
PERFORMANCE
RADIOACTIVITY
COOLING SYSTEMS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
ISOTOPES
MATERIALS
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
THERMAL REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated
PEACH BOTTOM-1 REACTOR
FISSION PRODUCTS
PRIMARY COOLANT CIRCUITS
VRAIN REACTOR
PERFORMANCE
RADIOACTIVITY
COOLING SYSTEMS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
ISOTOPES
MATERIALS
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
THERMAL REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated