Benchmark of Computational Fluid Dynamics Simulations Using Temperatures Measured Within Enclosed Vertical and Horizontal Arrays of Heated Rods-Reference-Cited by-同舟云学术

Benchmark of Computational Fluid Dynamics Simulations Using Temperatures Measured Within Enclosed Vertical and Horizontal Arrays of Heated Rods

Published:2009-09 Issue:3 Volume:167 Page:371-383
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Chalasani N. R.¹,Araya Pablo E.¹,Greiner Miles¹

Affiliation:

1. University of Nevada, Mechanical Engineering Department, Reno, Nevada

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT167-371

Reference18 articles.

1. “Characteristics of Spent Nuclear Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation,” DOE/RW-0184, U.S. Department of Energy, Office of Civilian Radioactive Waste Management (1987).

2. “GA-4 LegalWeight Truck From-Reactor Spent Fuel Shipping Cask, Safety Analysis Report for Packaging (SARP),” General Atomics (1998).

3. “Multi-Purpose Canister (MPC) Implementation Program Conceptual Design Phase Report,” DOC ID: A20000000-00811, Office of Civilian Radioactive Waste Management, U.S. Department of Energy (1993).

4. Use of Fuel Assembly/Backfill Gas Effective Thermal Conductivities to Predict Basket and Fuel Cladding Temperatures Within a Rail Package during Normal Transport

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