SLSF delayed neutron detection with the on-line sodium sampling system
Final design has been completed for a 1 gpm sodium sampling loop which will withdraw a continuous stream containing failed fuel in solution from the primary circuit of the Sodium Loop Safety Facility. Breeder reactor fuels are tested to destruction in the primary loop when inserted into the Engineering Test Reactor at INEL. Provisions for draining contaminated sodium to the primary loop permits a disconnect of the sampling loop after each test. The sampling loop will contain a delayed neutron monitor located remotely from the test fuels being irradiated; transit time will be 12s at rated flow. Fission products carried in sodium solution will emit delayed neutrons primarily of groups 2 and 3 (T/sub 1/2/ = 22s and 6s) in the monitor and provide a delivered efficiency of 7% for all delayed groups.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- Sponsoring Organization:
- Not Available; USDOE
- DOE Contract Number:
- EY-76-C-02-0016
- OSTI ID:
- 6267423
- Report Number(s):
- CONF-790816-5
- Country of Publication:
- United States
- Language:
- English
Similar Records
DN detection during SLSF tests
Modeling delayed neutron monitoring systems for fast breeder reactors
Related Subjects
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BARYONS
DELAYED NEUTRONS
DESIGN
DETECTION
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
ETR REACTOR
FAILED ELEMENT DETECTION
FERMIONS
FISSION NEUTRONS
HADRONS
IN PILE LOOPS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
NEUTRONS
NUCLEONS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAMPLING
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS