Development of a thermal analysis model for a nuclear spent fuel storage cask and experimental verification with prototype testing

Journal Article · Sun Oct 01 04:00:00 EDT 1989 · Journal of Engineering for Gas Turbines and Power; (USA)

DOI:https://doi.org/10.1115/1.3240306· OSTI ID:7052722

Hwang, J Y; Efferding, L E ^[1]

---

1. Westinghouse Electric Corp., Nuclear Components Div., Pensacola, FL (US)

A thermal analysis evaluation is presented of a nuclear spent fuel dry storage cask. The cask is designed to provide passive cooling of 24 pressurized water reactor (PWR) spent fuel assemblies for a storage period of at least 20 years at a nuclear utility site (independent spent fuel storage installation). A comparison is presented between analytical predictions and experimental results for a demonstration cask. Demonstration testing with nuclear spent fuel assemblies was performed on a cask configuration designed to store 24 intact spent fuel assemblies or canisters containing fuel consolidated from 48 assemblies.

• OSTI ID: 7052722
• Journal Information: Journal of Engineering for Gas Turbines and Power; (USA), Journal Name: Journal of Engineering for Gas Turbines and Power; (USA) Vol. 111:4; ISSN 0742-4795; ISSN JETPE
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
420400 -- Engineering-- Heat Transfer & Fluid Flow
DESIGN
PWR TYPE REACTORS
REACTORS
SPENT FUEL STORAGE
STORAGE
THERMAL ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR