|
E 1.99:wsrc-im--93-17-14
|
Environmental implementation plan Chapter 14, Environmental compliance tracking and data management. Revision. |
1 |
|
E 1.99:wsrc-im--93-017-16
|
Environmental implementation plan Chapter 16, Environmental appraisal and surveillance program. Draft revision. |
1 |
|
E 1.99:wsrc-im--93-17-20
|
Environmental implementation plan |
1 |
|
E 1.99:wsrc-im--94-26
|
Savannah River Site radionuclide air emissions annual report for national emission standards for hazardous air pollutants |
1 |
|
E 1.99:wsrc-im--94-28
|
Roadmap to the SRS computing architecture |
1 |
|
E 1.99:wsrc-im--94-39
|
History of 232-F, tritium extraction processing |
1 |
|
E 1.99:wsrc-im--94-42
|
Decommissioning of facilities at the Savannah River Site |
1 |
|
E 1.99:wsrc-m&o-2007-00040
|
PROJECTIZING AN OPERATING NUCLEAR FACILITY |
1 |
|
E 1.99:wsrc-ms--90-4
|
Factors affecting the retention of methyl iodide by iodide-impregnated carbon |
1 |
|
E 1.99:wsrc-ms-90-4
|
Factors affecting the retention of methyl iodide by iodide-impregnated carbon |
1 |
|
E 1.99:wsrc-ms-90-5
|
Savannah River Site L reactor testing |
1 |
|
E 1.99:wsrc-ms-90-9
|
Modifications to MELCOR for the analysis of heavy-water moderated, U-A1 fuel reactors |
1 |
|
E 1.99:wsrc-ms-90-10
|
A parametric model for analysis of melt progression in U-A1 assemblies |
1 |
|
E 1.99:wsrc-ms-90-11
|
A model for transient analysis of a multiple-medium confinement filter system |
1 |
|
E 1.99:wsrc-ms-90-15
|
Fission product release phenomena during core melt accidents in metal fueled heavy water reactors |
1 |
|
E 1.99:wsrc-ms-90-18
|
Metal-fueled HWR (heavy water reactors) severe accident issues Differences and similarities to commercial LWRs (light water reactors) |
1 |
|
E 1.99:wsrc-ms-90-20
|
The potential for fuel-target mixing during a fuel melting accident in an SRS fuel assembly |
1 |
|
E 1.99:wsrc-ms-90-21
|
Hydrogen isotope mass spectrometers |
1 |
|
E 1.99:wsrc-ms-90-27
|
Selection of a hydride former for the separation of hydrogen isotopes from inerts |
1 |
|
E 1.99:wsrc-ms--90-31
|
Rapid heating tensile tests of high-energy-rate-forged 316L stainless steel containing internal helium from radioactive decay of absorbed tritium |
1 |
