|
E 1.99: bnl-nureg--52168
|
Bias in peak clad temperature predictions due to uncertainties in modeling of ECC bypass and dissolved non-condensable gas phenomena |
1 |
|
E 1.99: bnl-nureg-52174
|
Safety evaluation of MHTGR licensing basis accident scenarios |
1 |
|
E 1.99: bnl-nureg--52178-vol.1
|
Age-related degradation of Westinghouse 480-volt circuit breakers |
1 |
|
E 1.99: bnl-nureg-52193
|
HTGR (High Temperature Gas-Cooled Reactor) ingress analysis using MINET |
1 |
|
E 1.99: bnl-nureg--52197
|
Summary of advanced LMR (Liquid Metal Reactor) evaluations PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor) |
1 |
|
E 1.99: bnl-nureg--52198
|
Reactivity accidents A reassessment of the design-basis events. |
1 |
|
E 1.99: bnl-nureg--52213
|
Evaluation of allowed outage times (AOTs) from a risk and reliability standpoint |
1 |
|
E 1.99:BNL-NUREG-52221
|
Assessment of candidate accident management strategies |
1 |
|
E 1.99: bnl-nureg--52222
|
Results from the Nuclear Plant Aging Research Program Their use in inspection activities. |
1 |
|
E 1.99: bnl-nureg--52257
|
Alternate modal combination methods in response spectrum analysis |
1 |
|
E 1.99: bnl-nureg--52259
|
Identification and assessment of containment and release management strategies for a BWR Mark I containment |
1 |
|
E 1.99: bnl-nureg--52260
|
Generic risk insights for Westinghouse and Combustion Engineering pressurized water reactors |
1 |
|
E 1.99: bnl-nureg--52261
|
Study of operational risk-based configuration control |
1 |
|
E 1.99: bnl-nureg--52282
|
Generic risk insights for General Electric boiling water reactors |
1 |
|
E 1.99: bnl-nureg--52288
|
Review of the Diablo Canyon probabilistic risk assessment |
1 |
|
E 1.99: bnl-nureg--52289
|
Estimate of radionuclide release characteristics into containment under severe accident conditions. Final report |
1 |
|
E 1.99: bnl-nureg--52295
|
Selection of models to calculate the LLW source term |
1 |
|
E 1.99: bnl-nureg--52297
|
THATCH A computer code for modelling thermal networks of high- temperature gas-cooled nuclear reactors. |
1 |
|
E 1.99: bnl-nureg--52303
|
Pilot program to assess proposed basic quality assurance requirements in the medical use of byproduct materials |
1 |
|
E 1.99: bnl-nureg--52309
|
Managing aging in nuclear power plants Insights from NRC maintenance team inspection reports. |
1 |
