TY - GEN
T1 - Application of a virtual reactivity feedback control loop in non-nuclear testing of a fast spectrum reactor
AU - Sitton, Shannon M.Bragg
AU - Forsbacka, Matthew
PY - 2004
Y1 - 2004
N2 - For a compact, fast-spectrum reactor, reactivity feedback is dominated by core deformation at elevated temperature. Given the use of accurate deformation measurement techniques, it is possible to simulate nuclear feedback in non-nuclear electrically heated reactor tests. Implementation of simulated reactivity feedback in response to measured deflection is being tested at the NASA Marshall Space Flight Center Early Flight Fission Test Facility (EFF-TF). During tests of the SAFE-100 reactor prototype, core deflection was monitored using a high resolution camera. "Virtual" reactivity feedback was accomplished by applying the results of Monte Carlo calculations (MCNPX) to core deflection measurements; the computational analysis was used to establish the reactivity worth of various core deformations. The power delivered to the SAFE-100 prototype was then adjusted accordingly via kinetics calculations. The work presented in this paper will demonstrate virtual reactivity feedback as core power was increased from 1 kW t to 10 kW t, held approximately constant at 10 kW t, and then allowed to decrease based on the negative thermal reactivity coefficient.
AB - For a compact, fast-spectrum reactor, reactivity feedback is dominated by core deformation at elevated temperature. Given the use of accurate deformation measurement techniques, it is possible to simulate nuclear feedback in non-nuclear electrically heated reactor tests. Implementation of simulated reactivity feedback in response to measured deflection is being tested at the NASA Marshall Space Flight Center Early Flight Fission Test Facility (EFF-TF). During tests of the SAFE-100 reactor prototype, core deflection was monitored using a high resolution camera. "Virtual" reactivity feedback was accomplished by applying the results of Monte Carlo calculations (MCNPX) to core deflection measurements; the computational analysis was used to establish the reactivity worth of various core deformations. The power delivered to the SAFE-100 prototype was then adjusted accordingly via kinetics calculations. The work presented in this paper will demonstrate virtual reactivity feedback as core power was increased from 1 kW t to 10 kW t, held approximately constant at 10 kW t, and then allowed to decrease based on the negative thermal reactivity coefficient.
UR - http://www.scopus.com/inward/record.url?scp=14844347931&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:14844347931
SN - 0894486802
SN - 9780894486807
T3 - Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
SP - 2259
EP - 2268
BT - Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
T2 - Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
Y2 - 13 June 2004 through 17 June 2004
ER -