Amanote Research
Register
Sign In
Discover open access scientific publications
Search, annotate, share and cite publications
Publications by W.L. Bunch
FFTF Shielding Program.
Discussion of Am-Cm Alpha Correction
Anticipated Heat Generation Rate of MGCR-III Fuel Element as a Function of Enrichment
Fission Product Inventory and Decay Heat Associated With FTR Fuel.
Determining Initial Composition of Regenerating In-Core Neutron Flux Detectors
Related publications
FFTF Pnl: Reliability Assurance Program Plan for the Fftf.
11 - FFTF-LMFBR Seal Test Program, October-December 1973
1 - FFTF-LMFBR Seal Test Program, July-Septeember 1974
FFTF Reactor-Characterization Program: Gamma-Ray Measurements and Shield Characterization
Structural Material Irradiations in FFTF
1998 FFTF Annual System Assessment Reports
FFTF Hybrid Computer System.
Recent Results on Fusion Reactor Materials From FFTF/MOTA Program. Neutron Dosimetry for Materials Irradiation Environment.
Kakuyūgō kenkyū
Modified Fermi Control Rod Latch for the Fftf: Report on the Development and Testing Program.
