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OCRWM Bulletin, August 1994

OCRWM Bulletin, August 1994 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 4

Book Description
The Civilian Radioactive Waste Management Program undertook a major initiative on June 3, 1994, by requesting proposals for a multi-purpose canister (MPC) system. The purpose of the system is to provide a standardized system for storage, transportation, and disposal of spent nuclear fuel. Among the advantages of the MPC concept two stand out. First, and most important, the system reduces handling of individual spent fuel assemblies. Second, it promotes standardization and compatibility among storage technologies used at civilian reactor storage sites and Department of Energy facilities. If used by the majority of reactors, the MPC will reduce total number of shipments and the overall waste management system costs for nuclear energy utilities and the Federal Government. The MPC concept calls for a sealed metal canister that can hold many spent fuel assemblies from a nuclear powerplant. The MPC system will be designed to provide criticality control, heat transfer, and structural support during storage and transportation of spent nuclear fuel. The canister will be placed inside separate units or ''over-packs'' for shipment, storage, and disposal. Nuclear Regulatory Commission (NRC) certificates of compliance are required for the MPC systems for storage and transportation . Ultimately, the waste package, which includes the MPC, systems for storage and transportation. Ultimately, the waste package, which includes the MPC, must be licensed by the NRC for disposal in a repository.

OCRWM Bulletin, August 1994

OCRWM Bulletin, August 1994 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 4

Book Description
The Civilian Radioactive Waste Management Program undertook a major initiative on June 3, 1994, by requesting proposals for a multi-purpose canister (MPC) system. The purpose of the system is to provide a standardized system for storage, transportation, and disposal of spent nuclear fuel. Among the advantages of the MPC concept two stand out. First, and most important, the system reduces handling of individual spent fuel assemblies. Second, it promotes standardization and compatibility among storage technologies used at civilian reactor storage sites and Department of Energy facilities. If used by the majority of reactors, the MPC will reduce total number of shipments and the overall waste management system costs for nuclear energy utilities and the Federal Government. The MPC concept calls for a sealed metal canister that can hold many spent fuel assemblies from a nuclear powerplant. The MPC system will be designed to provide criticality control, heat transfer, and structural support during storage and transportation of spent nuclear fuel. The canister will be placed inside separate units or ''over-packs'' for shipment, storage, and disposal. Nuclear Regulatory Commission (NRC) certificates of compliance are required for the MPC systems for storage and transportation . Ultimately, the waste package, which includes the MPC, systems for storage and transportation. Ultimately, the waste package, which includes the MPC, must be licensed by the NRC for disposal in a repository.

OCRWM Bulletin

OCRWM Bulletin PDF Author:
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 16

Book Description


Monthly Catalog of United States Government Publications

Monthly Catalog of United States Government Publications PDF Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages :

Book Description


Radioactive Waste Management

Radioactive Waste Management PDF Author:
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 726

Book Description


Monthly Catalogue, United States Public Documents

Monthly Catalogue, United States Public Documents PDF Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1828

Book Description


Yucca Mountain Site Characterization Project Bibliography, July-December 1994

Yucca Mountain Site Characterization Project Bibliography, July-December 1994 PDF Author: G. N. Cook
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 84

Book Description
Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Charactrization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Science and Technology Database from July 1, 1994 through December 31, 1994. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 782

Book Description


Industrial Development in Japan

Industrial Development in Japan PDF Author: Samia Mohammed El-Badry
Publisher:
ISBN:
Category : Industrialization
Languages : en
Pages : 252

Book Description


INIS Atomindex

INIS Atomindex PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 640

Book Description


Government Reports Announcements & Index

Government Reports Announcements & Index PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 620

Book Description