Call Number (LC) Title Results
E 1.99:pnl-4480 Equipment for nondestructive evaluation of the strength of the Fort St. Vrain core-support blocks 1
E 1.99:pnl-4481 Hanford beta-gamma personnel dosimeter prototypes and evaluation 1
E 1.99:pnl-4486 CAESCAP a computer code for compressed-air energy-storage-plant cycle analysis. 1
E 1.99:pnl-4487 Thermal outgassing of irradiated nuclear fuel a literature review. 1
E 1.99:pnl-4488 Thermal release of volatile fission products from irradiated nuclear fuel 1
E 1.99:pnl-4489 Methyl iodide sorption by reduced silver mordenite 1
E 1.99:pnl-4490 Recycle of iodine-loaded silver mordenite by hydrogen reduction 1
E 1.99: pnl-4491 Dose-projection considerations for emergency conditions at nuclear power plants 1
E 1.99:pnl-4498 Postulated licensing schedule for an independent spent fuel storage installation 1
E 1.99:pnl-4499 Survey and analysis of federally developed technology 1
E 1.99:pnl-4505 Preliminary overview of innovative industrial-materials processes 1
E 1.99:pnl-4506 User's guide for the BNW-III optimization code for modular dry/wet-cooled power plants 1
E 1.99: pnl-4507 Investigation into the feasibility of alternative plutonium shipping forms 1
E 1.99: pnl-4509 Evaluation of experiences in long-term radon and radon-daughter measurements 1
E 1.99: pnl-4510-vol.1 Interactive Rapid Dose Assessment Model (IRDAM) user's guide. 1
E 1.99: pnl-4510-vol.2 Interactive Rapid Dose Assessment Model (IRDAM) reactor-accident assessment methods. Vol. 2. 1
E 1.99: pnl-4510-vol.3 Interactive Rapid Dose Assessment Model (IRDAM) scenarios for comparing dose-assessment models. Vol. 3. 1
E 1.99:pnl-4513 Fiscal implications of a 1-mill/kWh waste management fee 1
E 1.99:pnl-4515 Guidelines for the calibration of personnel dosimeters 1
E 1.99: pnl-4516 Evaluation of the Split-H approach to modeling non-buoyant releases from vent stacks 1