Application of Monte Carlo Neutron Photon to Hanford Waste Vitrification Plant Design Analysis

by L. L. Carter, Westinghouse Hanford Co, Richland, United States,
J. A. Caggiano, Westinghouse Hanford Co, Richland, United States,
T. Chiao, Westinghouse Hanford Co, Richland, United States,
J. Greenborg, Westinghouse Hanford Co, Richland, United States,
R. J. Morford, Westinghouse Hanford Co, Richland, United States,
R. E. Schenter, Westinghouse Hanford Co, Richland, United States,
G. J. Mroz, Westinghouse Hanford Co, Richland, United States,
R. B. Spencer, Westinghouse Hanford Co, Richland, United States,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1993

Abstract:

The Monte Carlo Neutron Photon (MCNP) computer program ('MNCP - A General Monte Carlo Code for Neutron and Photon Transport, Version 3A') (in PC and mainframe versions) has been used for the Hanford Waste Vitrification Plant (HWVP) design and operational exposure assessments, including the glass melter cell, the canister storage pit, the shielded canister transporter, and other facilities.

Subject Headings: Waste storage | Industrial facilities | Heat treatment | Waste disposal | Radioactive wastes | Monte Carlo method | Computer aided design

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