E 1.99:CONF-970607--1
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Design basis event consequence analyses for the Yucca Mountain project |
1 |
E 1.99: conf-970607--2
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Isotope production target irradiation experience at the annular core research reactor |
1 |
E 1.99:CONF-970607--3
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Physics of the ²⁵²Cf-source-driven noise analysis measurement |
1 |
E 1.99: conf-970607--4
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Adaptation of a neutron diffraction detector to coded aperture imaging |
1 |
E 1.99:CONF-970607--5
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Preliminary radiation transport analysis for the proposed National Spallation Neutron Source (NSNS) |
1 |
E 1.99:CONF-970607--6
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Applying x-ray digital imaging to the verification of cadmium in fuel-storage components |
1 |
E 1.99:CONF-970607--7
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COMSORS A light water reactor chemical core catcher. |
1 |
E 1.99:CONF-970607--8
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Isotopic biases for actinide-only burnup credit |
1 |
E 1.99:CONF-970607--9
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Criticality validation for burnup credit using recycle Pu criticals |
1 |
E 1.99:CONF-970607--10
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Appropriate burnup measurements for transportation burnup credit |
1 |
E 1.99:CONF-970607--11
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End effect K{sub eff} bias curve for actinide-only burnup credit casks |
1 |
E 1.99:CONF-970607--12
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Overview of the NSNS target station |
1 |
E 1.99:CONF-970607--13
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KENO lifetimes |
1 |
E 1.99:CONF-970607--14
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Definition of neutron lifespan and neutron lifetime in MCNP4B |
1 |
E 1.99:CONF-970607--15
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Measurement of the equivalent fundamental-mode source strength |
1 |
E 1.99:CONF-970607--16
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Comparison of neutron lifetimes as predicted by MCNP and DANTSYS |
1 |
E 1.99:CONF-970607--17
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Hydrological methods preferentially recover cesium from nuclear waste salt cake |
1 |
E 1.99:CONF-970607--18
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TCE field-scale simulation using immobile-mobile waste phase model |
1 |
E 1.99:CONF-970607--20
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Relationship between k{sub eff} and the fraction of critical mass |
1 |
E 1.99:CONF-970607--21
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Nuclear criticality safety staff training and qualifications at Los Alamos National Laboratory |
1 |