SPENT NUCLEAR FUEL NUMBER DENSITIES FOR MULTI-PURPOSE CANISTER CRITICALITY CALCULATIONS | Zendy

D. A. Thomas | Zendy

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SPENT NUCLEAR FUEL NUMBER DENSITIES FOR MULTI-PURPOSE CANISTER CRITICALITY CALCULATIONS

Author(s) -

D. A. Thomas

Publication year - 1996

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/891576

Subject(s) - criticality , nuclear engineering , nuclear criticality safety , spent nuclear fuel , failure mode, effects, and criticality analysis , conceptual design , environmental science , nuclear material , computer science , reliability engineering , engineering , nuclear physics , physics , mechanical engineering

The purpose of this analysis is to calculate the number densities for spent nuclear fuel (SNF) to be used in criticality evaluations of the Multi-Purpose Canister (MPC) waste packages. The objective of this analysis is to provide material number density information which will be referenced by future MPC criticality design analyses, such as for those supporting the Conceptual Design Report

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