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

Radulescu, G.

United States. Department of Energy. Yucca Mountain Project Office.

关键词: 11 Nuclear Fuel Cycle And Fuel Materials;    Shielding;    Wastes;    N-Reactor;    Glass;   

DOI  :  10.2172/893799
RP-ID  :  CAL-DDC-NU-000002 Rev. 00
RP-ID  :  NA
RP-ID  :  893799

美国|英语

来源: UNT Digital Library

【 摘 要 】

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. The scope of this calculation is limited to reporting dose rates averaged over segments of the WP radial and axial surfaces and of surfaces 1 m and 2 m from the WP. The results of this calculation will be used to assess the shielding performance of the 2-MC012-DHLW WP engineering design.