Operational Testing Highlights of Fort St. Vrain
Conference
·
OSTI ID:4155778
- General Atomics, San Diego, CA (United States)
- Public Service Company of Colorado, Denver, CO (United States)
The Fort St. Vrain program has progressed through construction, preoperational testing, fuel loading, initial criticality, and operational testing at power levels up to 2 percent related power. To date, all tests necessary before the rise to full power have been completed, and the rise-to-power program is expected to be resumed again in late 1975. Major plant systems, including the prestressed concrete reactor vessel and circulators, have demonstrated adequate performance. Extensive tests on the reactor core at zero power and up to 2 percent power have demonstrated the accuracy in the design predictions of such core characteristics as critical rod position, control system worths, neutron flux distributions, and temperature coefficients. Gaseous fission product release measurements to date have confirmed the extensive analytical estimates.
- Research Organization:
- General Atomics, San Diego, CA (United States); Public Service Company of Colorado, Denver, CO (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Energy Research and Development Administration (ERDA)
- DOE Contract Number:
- E(04-3)-633
- NSA Number:
- NSA-33-011229
- OSTI ID:
- 4155778
- Report Number(s):
- GA-A--13602; CONF-751007--7
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*VRAIN REACTOR-- TESTING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTROL ROD WORTHS
Circulators
Core Fabrication
Fission Gas Release Measurement
Fuel Loading and Handling
Fuel and Reactor Core
Gaseous Fission Product Release Measurements
High-Temperature Gas-Cooled Reactor (HTGR)
Hot Functional Tests
Moisture Ingress
Nuclear Criticality Safety Program (NCSP)
Pelton Wheels
Plant History
Plant Systems
REACTOR COMPONENTS
REACTOR KINETICS
Radial Peaking Factors (RPF)
STEAM SYSTEMS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTROL ROD WORTHS
Circulators
Core Fabrication
Fission Gas Release Measurement
Fuel Loading and Handling
Fuel and Reactor Core
Gaseous Fission Product Release Measurements
High-Temperature Gas-Cooled Reactor (HTGR)
Hot Functional Tests
Moisture Ingress
Nuclear Criticality Safety Program (NCSP)
Pelton Wheels
Plant History
Plant Systems
REACTOR COMPONENTS
REACTOR KINETICS
Radial Peaking Factors (RPF)
STEAM SYSTEMS