Volume 107
Number 2
Preparation, Conduct, and Experimental Results of the AVR Loss-of-Coolant Accident Simulation Test
Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 99-113
Technical Paper / dx.doi.org/10.13182/NSE91-A15725
Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 114-130
Technical Paper / dx.doi.org/10.13182/NSE91-A15726
Use of Qualitative and Quantitative Models in the Supervision of Power Plant Operations
Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 131-141
Technical Paper / dx.doi.org/10.13182/NSE91-A15727
KNOWBOT: An Adaptive Data Base Interface
Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 142-157
Technical Paper / dx.doi.org/10.13182/NSE91-A15728
Adaptive Predictive Control of a Boiling Water Reactor
Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 158-172
Technical Paper / dx.doi.org/10.13182/NSE91-A15729
A Mechanism for Out-of-Phase Power Instabilities in Boiling Water Reactors
Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 173-179
Technical Note / dx.doi.org/10.13182/NSE91-A15730
Monte Carlo Analysis of a Neutron Streaming Experiment
Nuclear Science and Engineering / Volume 107 / Number 2 / February 1991 / Pages 180-187
Technical Note / dx.doi.org/10.13182/NSE91-A15731
