The objective of this calculation is to perform additional degraded mode criticality evaluations of the Department of Energy's (DOE) Fast Flux Test Facility (FFTF) Spent Nuclear Fuel (SNF) codisposed in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP). The scope of this calculation is limited to the most reactive degraded configurations of the codisposal WP with an almost intact Ident-69 container (breached and flooded but otherwise non-degraded) containing intact FFTF SNF pins. The configurations have been identified in a previous analysis (CRWMS M&O 1999a) and the present evaluations include additional relevant information that was left out of the original calculations. The additional information describes the exact distributi...
Although idealized calculations of the potential for an atomic explosion within a repository can mak...
The Department of Energy's (DOE's) National Spent Nuclear Fuel Program is developing a standardized ...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
The objective of this calculation is to characterize the nuclear criticality safety concerns associa...
The purpose of this calculation is to perform intact mode and partially degraded mode criticality ev...
The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling F...
The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's...
An assessment has been performed of the criticality potential associated with the disposal of spent ...
The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA...
This study is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Depart...
The ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003) presents the methodology...
The purpose of this design calculation is to demonstrate that the handling operations of transportat...
Assessment of nuclear criticality potential of the S-Area Defense Waste Processing Facility (DWPF) i...
This design calculation updates the previous criticality evaluation for the fuel handling, transfer,...
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WP...
Although idealized calculations of the potential for an atomic explosion within a repository can mak...
The Department of Energy's (DOE's) National Spent Nuclear Fuel Program is developing a standardized ...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
The objective of this calculation is to characterize the nuclear criticality safety concerns associa...
The purpose of this calculation is to perform intact mode and partially degraded mode criticality ev...
The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling F...
The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's...
An assessment has been performed of the criticality potential associated with the disposal of spent ...
The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA...
This study is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Depart...
The ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003) presents the methodology...
The purpose of this design calculation is to demonstrate that the handling operations of transportat...
Assessment of nuclear criticality potential of the S-Area Defense Waste Processing Facility (DWPF) i...
This design calculation updates the previous criticality evaluation for the fuel handling, transfer,...
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WP...
Although idealized calculations of the potential for an atomic explosion within a repository can mak...
The Department of Energy's (DOE's) National Spent Nuclear Fuel Program is developing a standardized ...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...