The purpose of this calculation is to perform intact mode and partially degraded mode criticality evaluations of the Department of Energy's (DOE) Enrico Fermi (EF) Spent Nuclear Fuel (SNF) co-disposed in a 5 Defense High-Level Waste (5-DHLW) Waste Package (WP) and emplaced in a Monitored Geologic Repository (MGR). The criticality evaluations estimate the values of the effective neutron multiplication factor, k{sub eff}, a measure of nuclear criticality potential, for the 5-DHLW/DOE SNF WP with intact or partially degraded internal configurations. These evaluations contribute to the WP design
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling F...
The objective of this calculation is to perform additional degraded mode criticality evaluations of ...
The objective of this calculation is to characterize the nuclear criticality safety concerns associa...
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 ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003) presents the methodology...
Criticality analysis of the proposed melt-dilute (MD) form of aluminum-based spent nuclear fuel (SNF...
International audienceThe current prospect of reprocessing the assemblies of the PHENIX Fast-neutron...
The fuel composition of the Generation IV 600 MWth 'efficient' Gas Cooled Fast Reactor (GCFR) that r...
The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA...
Although idealized calculations of the potential for an atomic explosion within a repository can mak...
This report presents the basis for grouping the over 250 Department of Energy (DOE) spent nuclear fu...
This study is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Depart...
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling F...
The objective of this calculation is to perform additional degraded mode criticality evaluations of ...
The objective of this calculation is to characterize the nuclear criticality safety concerns associa...
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 ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003) presents the methodology...
Criticality analysis of the proposed melt-dilute (MD) form of aluminum-based spent nuclear fuel (SNF...
International audienceThe current prospect of reprocessing the assemblies of the PHENIX Fast-neutron...
The fuel composition of the Generation IV 600 MWth 'efficient' Gas Cooled Fast Reactor (GCFR) that r...
The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA...
Although idealized calculations of the potential for an atomic explosion within a repository can mak...
This report presents the basis for grouping the over 250 Department of Energy (DOE) spent nuclear fu...
This study is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Depart...
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling F...