A method for inhibiting the deposition of radioactive cobalt in a water-bearing vessel of a water... more A method for inhibiting the deposition of radioactive cobalt in a water-bearing vessel of a water-cooled nuclear reactor is described comprising: adding zinc oxide to water entering the water-bearing vessel, continuously during operation of the water-cooled nuclear reactor.
Since serious corrosion problems that have plagued the light water reactor (LWR) industry for dec... more Since serious corrosion problems that have plagued the light water reactor (LWR) industry for decades. The complex corrosion mechanisms involved and the development of practical engineering solutions for their mitigation will discussed. After a brief discussion of the basic designs of the boiling water reactor (BWR) and pressurized water reactor (PWR), emphasis will be placed on the general corrosion of LWR containments, flow-accelerated corrosion of carbon steel components, intergranular stress corrosion cracking (IGSCC) in BWRs, primary water stress corrosion cracking (PWSCC) in PWRs and irradiation assisted stress corrosion cracking (IASCC) in both systems. Finally, the corrosion future of both plants will be discussed as plants extend their period of operation for an additional 20 to 40 years.
A method for inhibiting the deposition of radioactive cobalt in a water-bearing vessel of a water... more A method for inhibiting the deposition of radioactive cobalt in a water-bearing vessel of a water-cooled nuclear reactor is described comprising: adding zinc oxide to water entering the water-bearing vessel, continuously during operation of the water-cooled nuclear reactor.
Since serious corrosion problems that have plagued the light water reactor (LWR) industry for dec... more Since serious corrosion problems that have plagued the light water reactor (LWR) industry for decades. The complex corrosion mechanisms involved and the development of practical engineering solutions for their mitigation will discussed. After a brief discussion of the basic designs of the boiling water reactor (BWR) and pressurized water reactor (PWR), emphasis will be placed on the general corrosion of LWR containments, flow-accelerated corrosion of carbon steel components, intergranular stress corrosion cracking (IGSCC) in BWRs, primary water stress corrosion cracking (PWSCC) in PWRs and irradiation assisted stress corrosion cracking (IASCC) in both systems. Finally, the corrosion future of both plants will be discussed as plants extend their period of operation for an additional 20 to 40 years.
Uploads
Papers by Barry Gordon