| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99:CONF-971118--1 | An in-house alternative to traditional SDI services at Argonne National Laboratory | 1 |
| E 1.99: conf-971119--1 | A top-down approach to high-consequence fault analysis for software systems | 1 |
| E 1.99:CONF-971121-- |
The art of implosions has impacted the success of three decontamination and decommissioning projects at Fernald Radiological survey techniques for decontamination and dismantlement applications Incorporation of pollution prevention and waste minimization practices during the decommissioning of Building 310 at Argonne National Laboratory-East |
3 |
| E 1.99:CONF-971123-- |
Multi-mutational model for cancer based on age-time patterns of radiation effects 2. Biological aspects. Chromosome aberrations in lymphocytes of workers occupationally exposed to ionising radiation |
2 |
| E 1.99: conf-971125-- |
EBR-II spent fuel treatment demonstration project Measurements of interfacial area concentration in two-phase bubbly flow Exponential Discontinuous Solution of the Multispecies Relativistic Heavy Ion Transport Equations Vitrification of actinides contained in platinum alloy vessels Mo-99 production at the Annular Core Research Reactor - recent calculative results Waste Processing To Support ⁹⁹Mo Production at Sandia National Laboratories Application of the ARRAMIS Risk and Reliability Software to the Nuclear Accident Progression An Efficient Method for Heavy Ion Dose Calculations Spallation products in the Accelerator Production of Tritium device Chemical Processing and Production of ⁹⁹Mo at Sandia National Laboratories |
10 |
| E 1.99:CONF-971125*-- | Addressing nuclear and hostile environment challenges with intelligent automation | 1 |
| E 1.99:CONF-971125-- |
Performance of scientific computing platforms running MCNP4B Value of burnup credit beyond actinides Initial results of metal waste form development activities at ANL-West The MCNP{trademark}/LCS{trademark} merger project Neutronic design of the APT Target/Blanket An epithermal neutron source for BNCT based on an ESQ-accelerator Derivation of criticality safety benchmarks from ZPR fast critical assemblies Converting ⁹⁹Mo production from high- to low-enriched uranium Spallation source materials test program Considerations in using third order focusing of proton beams for uniform irradiation of extended targets Dart model for irradiation-induced swelling of dispersion fuel elements including aluminum-fuel interaction Application of the electrometallurgical treatment technique to long-term disposition of DOE spent fuel Second Order Perturbations of Monte Carlo Criticality Calculations Ion transport calculations using MCNP Collimator design for the NSNS accumulator ring Thermal-hydraulic performance of a water-cooled tungsten-rod target for a spallation neutron source Accelerator transmutation of waste blanket considerations Occupational radiation dose assessment for a non site specific spent fuel storage facility Measurement of high energy neutrons via Lu(n,xn) reactions Technical information resources for criticality safety Neutronics analysis of three beam-filter assemblies for an accelerator-based BNCT facility APT target-blanket fabrication development Proposed subcritical measurements for fresh and spent highly enriched plate type fuel assemblies Radiation analysis for a generic centralized interim storage facility Thick-target neutron, gamma-ray, and radionuclide production for protons below 12 MeV on nickel and carbon beam-stops Nuclear data libraries for incident neutrons and protons to 150 MeV in ENDF-6 format Effects on the long term storage container by thermal cycling alpha plutonium Extraction of hydrogenous material from cemented wasteforms by supercritical fluid carbonation Burn-up and neutron economy of accelerator-driven reactor New calculations for critical assemblies using MCNP4B Simultaneous Monte Carlo zero-variance estimates of several correlated means Beam shut down considerations for large accelerator-driven target systems Deterministic proton transport solving a one dimensional Fokker-Planck equation Target/Blanket Design for the Accelerator Production of Tritium Plant Exponential convergence with adaptive Monte Carlo Tritium implantation in the accelerator production of tritium device Thermal-hydraulic design of the target/blanket for the accelerator production of tritium conceptual design Tritium production distribution in the accelerator production of tritium device DOE EM industry programs robotics development Back end of an enduring fuel cycle Preliminary earth berm shielding calculations for the accelerator production of tritium 1700-MeV accelerator Skeletons in the closet Implementation of the packaging program at Los Alamos. Observations regarding fixed decay constants on the reactivity prediction for the fast fission of U-235 Further investigation of spectral temperature feedbacks Alpha-like calculations with MCNP Effect of compositional variation in plutonium on process shielding design Two-dimensional benchmark calculations for PNL-30 through PNL-35 Quantifying the severity of criticality limit violations Reactor beam calculations to determine optimum delivery of epithermal neutrons for treatment of brain tumors Multi-group Fokker-Planck proton transport in MCNP{trademark} Accelerator production of tritium plant design and supporting engineering development and demonstration work LAHET code system benchmarking in the accelerator production of tritium November 1995 small scale tritium production experiment |
52 |
| E 1.99:conf-971125-- | Enduring Nuclear Fuel Cycle, Proceedings of a panel discussion | 1 |
| E 1.99:CONF-971125--1 | Radiation analysis for a generic centralized interim storage facility | 1 |
| E 1.99: conf-971125--2 | Food and Drug Administration process validation activities to support 99Mo production at Sandia National Laboratories | 1 |
| E 1.99:CONF-971125--3 | High sensitivity gamma spectrometry of air samples near SRS during 1985-1995 | 1 |
| E 1.99: conf-971125--4 | Production of fission and activation product isotopes at Sandia National Laboratories | 1 |
| E 1.99: conf-971125--5 | Hot Cell Facility modifications at Sandia National Laboratories to support ⁹⁹Mo production | 1 |
| E 1.99: conf-971125--6 | Development and assessment of the CONTAIN hybrid flow solver | 1 |
| E 1.99: conf-971125--7 | A method for establishing integrity in software-based systems | 1 |
| E 1.99:CONF-971125--8 | Two delayed critical uranium (93.2) metal cylindrical annuli with central Be moderation | 1 |
| E 1.99:CONF-971125--9 | Storage array reflection considerations | 1 |
| E 1.99: conf-971125--10-summ | Fused-salt-liquid-metal corrosion of refractory alloys in the presence of hot cell impurities | 1 |
| E 1.99:CONF-971125--11-Summ | Argonne National Laboratorỳs photo-oxidation organic mixed waste treatment system - installation and startup testing | 1 |
| E 1.99:CONF-971125--12-Summ | The restoration of an Argonne National Laboratory foundry | 1 |
