E 1.99: conf-920307--97
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Westinghouse-DOE integration Meeting the challenge. |
1 |
E 1.99: conf-920307--99
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Environmental monitoring and cooperative resource management at the WIPP site |
1 |
E 1.99: conf-920307--100
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Simulation model for the WIPP transportation and delivery system |
1 |
E 1.99: conf-920307--101
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Fluid flow through very low permeability materials A concern in the geological isolation of waste. |
1 |
E 1.99: conf-920307--103
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Accelerated clean-up at the Hanford Site |
1 |
E 1.99: conf-920307--104
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Comparison of computer codes and inputs used at DOE sites to model intrusion scenarios |
1 |
E 1.99: conf-920307--extd.abst
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The WIPP decision plan Charting the course for openness in the decision making process. |
1 |
E 1.99: conf-920308--1
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Validation of the REBUS-3/RCT methodologies for EBR-II core-follow analysis |
1 |
E 1.99:conf-920308-3
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Development of High Flux Isotope Reactor (HFIR) subcriticality monitoring methods |
1 |
E 1.99: conf-920308--4
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A variable timestep generalized Runge-Kutta method for the numerical integration of the space-time diffusion equations |
1 |
E 1.99: conf-920308--5
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Calculation of the Fast Flux Test Facility fuel pin tests with the WIMS-E and MCNP codes |
1 |
E 1.99:conf-920308--6
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Monitoring nuclear reactor systems using neural networks and fuzzy logic |
1 |
E 1.99: conf-920308--8
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Calculational benchmark comparisons for a low sodium void worth actinide burner core design |
2 |
E 1.99: conf-920308--9
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Comparative neutronic analysis of Pb-versus Na-cooled LMR cores |
2 |
E 1.99: conf-920308--10
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Feedback components of a U20Pu10Zr-fueled compared to a U10Zr-fueled EBR-II |
2 |
E 1.99: conf-920308--11
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An improved quasistatic option for the DIF3D nodal kinetics code |
2 |
E 1.99: conf-920308--12
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An evaluation of multigroup flux predictions in the EBR-II core |
2 |
E 1.99: conf-920308--13-rev.1
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Confirming criticality safety of TRU waste with neutron measurements and risk analyses |
2 |
E 1.99: conf-920308--14
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Re-evaluation of Savannah River reactor transient reactivity coefficient tests The effect of delayed neutron constants and spatial variations. |
2 |
E 1.99: conf-920308--15
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A study of temperature coefficients of reactivity for a Savannah River Site tritium-producing charge |
2 |