Category of Content

Siting Experience Documents Only

Publication Date

Subject Matter

Keywords

Displaying 1 - 19 of 19

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Author(s)
OCRWM
Publication Date
The objective of this calculation is to determine the dose rates on the external surfaces of the waste package (WP) containing two Hanford defense high-level waste (DHLW) glass canisters and two Hanford multi-canister overpacks (MCO). Each MCO is loaded with the N Reactor spent nuclear fuel (SNF). The information provided by the sketches attached to this calculation is that of the potential design for the WP type considered in this calculation.
high level waste radiation protection storage hanford site 2-mco/2-dhlw dose calculation multi-canister overpack defense

WHF and RF Thermal Evaluation

WHF and RF Thermal Evaluation

Author(s)
Bechtel SAIC Company, LLC
Publication Date
The purpose of this analysis is to estimate the peak fuel assembly cladding temperature within the transportation casks that will be received in the WHF and RF, and to compare this value with established temperature limits. Thermally limiting scenarios are evaluated for both normal and off-normal operating conditions, with the off-normal condition defined as a loss of active ventilation. A second purpose of this analysis is to identify a specific room in the surface facilities as thermally limiting of all the rooms, with respect to the potentially highest temperatures on the concrete walls.
thermal analysis transportation yucca mountain heat load

Waste Package Neutron Absorber, Thermal Shunt, and Fill Gas Selection Report

Waste Package Neutron Absorber, Thermal Shunt, and Fill Gas Selection Report

Author(s)
CRWMS M&O
Publication Date
Materials for neutron absorber, thermal shunt, and fill gas for use in the waste package were selected using a qualitative approach. For each component, selection criteria were identified; candidate materials were selected; and candidates were evaluated against these criteria. The neutron absorber materials evaluated were essentially boron-containing stainless steels. Two candidates were evaluated for the thermal shunt material. The fill gas candidates were common gases such as helium, argon, nitrogen, carbon dioxide, and dry air.
yucca mountain neutron absorbers waste package design b00000000-01717-2200-00227 thermal shunt fill gas

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update

Author(s)
U.S. Nuclear Waste Technical Review Board
Publication Date

In October 2009, the U.S. Nuclear Waste Technical Review Board (Board or NWTRB) published Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel.  For each of the 13 national programs studied, the report catalogued 15 institutional arrangements that had been set in place and 15 technical approaches that had been taken to design repository systems for the long-term management of high-activity radioactive waste.

Gateway for Accelerated Innovation in Nuclear (GAIN) Website

Gateway for Accelerated Innovation in Nuclear (GAIN) Website

Author(s)
Gateway for Accelerated Innovation in Nuclear
Publication Date

Website for Gateway for Accelerated Innovation in Nuclear (GAIN).

The mission of the Department of Energy Office of Nuclear Energy (DOE-NE) is to advance nuclear power as a resource capable of meeting the nation's energy, environmental and national security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development and demonstration ﴾RD&D﴿.

Disclaimer: Note that this page contains links to external sites. When leaving the CURIE site, please note that the U.S. Department of Energy and Pacific Northwest National Laboratory do not control or endorse the content or ads on these sites.
Sponsored by: