THIS REPORT IS MAINLY CONCERNED WITH FORGINGS MADE FROM MARTENSITIC STEELS HEAT TREATED TO STRENGTHS RANGING FROM 240,000 TO 300,000 PSI. FORGING CHARACTERISTICS, DESIGN LIMITATIONS, DIMENSIONAL TOLERANCES, AND QUALITY-CONTROL PROBLEMS ARE DISCUSSED. A CONSIDERABLE AMOUNT OF DATA ON MECHANICAL PROPERTIES IS ALSO PRESENTED. IN ADDITION, THE REPORT SUMMARIZES THE AVAILABLE INFORMATION ON FORGED, SEMIAUSTENITIAL STEELS. THIS COMPILATION IS BASED ON PUBLISHED ARTICLES, GOVERNMENT REPORTS, AND INTERVIEWS WITH PRODUCERS AND USERS OF STEEL FORGINGS.

High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.

Because of a special interest in Alloy 718, the Defense Metals Information Center has summarized information on the welding and brazing of the alloy. Two principal resons for the interest in this alloy are its good formability and its good weldability, expecially under restraint. The greater portion of the fusion welding of Alloy 718 has been done by the gas tungsten-arc (TIG) process. A discussion of welding atmosphere, filler metals, heat treatment of welds, welding under restraint, and weld toughness is presented in the section on fusion welding. Information is also presented on resistance welding and electron-beam welding of Alloy 718. The final section of this report deals with the brazing of Alloy 718.

The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).