An experimental and calculational study has been performed to understand and prevent inadvertent activation of the criticality alarm system (CAS) from fuel-handling operations at the Irradiated Fuel Storage Facility. In conjunction with the study, the CAS neutron detectors were tested to verify the design specifications for gamma rejection capability and zero response limit. A minimum physical restrictive boundary around the CAS location was established based on a gamma ray dose rate limit of 10 rad/hr. The canister loaded with spent nuclear fuel must be moved in the area outside the exclusion zone so as not to trigger a false alarm from the CAS detectors
International audienceNuclear measurements are used at AREVA NC/La Hague for the monitoring of spent...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...
An experimental and calculational study has been performed to understand and prevent inadvertent act...
This is a preprint of a paper intended for publication in a journal or proceedings. Since changes ma...
Neutron-sensitive radiation detectors are used in the Portsmouth Gaseous Diffusion Plant`s (PORTS) c...
With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU...
Under the current climate of increasing regulation and decreasing budgets, DOE nuclear facilities ar...
Criticality alarm systems (CASs) are mandatory in nuclear plants for prompt alarm in the event of an...
This report documents the criticality safety evaluation for the storage of PWR spent nuclear fuel in...
The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling F...
In most cases, gamma radiation is the dominant dose contributor, but in specific configurations, neu...
The Portsmouth Gaseous Diffusion Plant (PORTS) is leased from the US Department of Energy (DOE) by t...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
The paper discusses the stages of calculating the radiation safety of spent nuclear fuel (SNF) trans...
International audienceNuclear measurements are used at AREVA NC/La Hague for the monitoring of spent...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...
An experimental and calculational study has been performed to understand and prevent inadvertent act...
This is a preprint of a paper intended for publication in a journal or proceedings. Since changes ma...
Neutron-sensitive radiation detectors are used in the Portsmouth Gaseous Diffusion Plant`s (PORTS) c...
With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU...
Under the current climate of increasing regulation and decreasing budgets, DOE nuclear facilities ar...
Criticality alarm systems (CASs) are mandatory in nuclear plants for prompt alarm in the event of an...
This report documents the criticality safety evaluation for the storage of PWR spent nuclear fuel in...
The purpose of this design calculation is to perform a criticality evaluation of the Fuel Handling F...
In most cases, gamma radiation is the dominant dose contributor, but in specific configurations, neu...
The Portsmouth Gaseous Diffusion Plant (PORTS) is leased from the US Department of Energy (DOE) by t...
This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both...
The paper discusses the stages of calculating the radiation safety of spent nuclear fuel (SNF) trans...
International audienceNuclear measurements are used at AREVA NC/La Hague for the monitoring of spent...
The development of the Pebble Bed Modular Reactor entails the design of numerous systems for various...
Damaged fuels originated from the accident at the Fukushima-Daiichi Nuclear Power Station, and the s...