The Fissile Material Disposition Program Light Water Reactor Mixed Oxide Fuel Irradiation Test Project Plan details a series of test irradiations designed to investigate the use of weapons-grade plutonium in MOX fuel for light water reactors (LWR) (Cowell 1996a, Cowell 1997a, Thoms 1997a). Commercial MOX fuel has been successfully used in overseas reactors for many years; however, weapons-derived test fuel contains small amounts of gallium (about 2 parts per million). A concern exists that the gallium may migrate out of the fuel and into the clad, inducing embrittlement. For preliminary out-of-pile experiments, Wilson (1997) states that intermetallic compound formation is the principal interaction mechanism between zircaloy cladding and gallium. This interaction is very limited by the low mass of gallium, so problems are not expected with the zircaloy cladding, but an in-pile experiment is needed to confirm the out-of-pile experiments. Ryskamp (1998) provides an overview of this experiment and its documentation. The purpose of this Experiment Safety Assurance Package (ESAP) is to demonstrate the safe irradiation and handling of the mixed uranium and plutonium oxide (MOX) Fuel Average Power Test (APT) experiment as required by Advanced Test Reactor (ATR) Technical Safety Requirement (TSR) 3.9.1 (LMITCO 1998). This ESAP addresses the specific operation of the MOX Fuel APT experiment with respect to the operating envelope for irradiation established by the Upgraded Final Safety Analysis Report (UFSAR) Lockheed Martin Idaho Technologies Company (LMITCO 1997a). Experiment handling activities are discussed herein.

Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.

Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.

The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR