[en] For many large ferritic steel pressure vessels, assurance of continued safe operation depends on the fracture toughness properties of the base metals and weld metals which are used in the vessel fabrication. The testing procedure discussed in this paper was developed for nuclear pressure vessel steels and their weldments. Consequently these materials served as the basis for the development of the procedure. The procedure is applicable to any steel and hence 2/one quarter/ Cr-1 Mo (A 387 grade D) and C-Mn-Si (A 212 grade B) steels were included in this study. 11 refs

No abstract available

[en] Tank 22 (a 1,300,000-gallon Type IV tank) was placed in service June 6, 1965, receiving HW from tank 21. The HW was transferred back into tank 21 in September 1965 and fed to the Building 242-H evaporator. This recycled concentrate and concentrate from other waste was then received in tank 22 until the tank was filled. The HW concentrate and salt remained in the tank until November 1971 when removal was begun. The concentrated supernate was transferred from the tank followed by dissolution and removal of salt from the tank walls and bottom. The salt removal was completed in May 1974 and since that time tank 22 has served as a receiver of LW from Building 221-H. Inspections of the tank interior were made using a 40-ft optical periscope and the steel thickness of the tank bottom was measured ultrasonically. Samples of the tank vapors and liquid collected in the sidewall and bottom sumps were analyzed. Temperature and specific gravity measurements were made of waste stored in the tank. Several equipment modifications and repairs were made

[en] Irradiation hardening is an issue of practical importance as it relates to the remanent life and the nature of failure of reactor components exposed to displacement-producing radiation. Understanding these phenomena requires studies of fundamental microstructural mechanisms of hardening. In this paper, the authors analyze the tensile behavior of pressure vessel steels (A212B and A350) irradiated by neutrons and electrons. The results show that the post-yield true stress/true strain behavior can provide fingerprints of the different hardening effects that result from irradiation by the two particles, which suggests correspondingly different hardening microstructures for the two particles. Micro-structurally-based models for irradiation-induced yield strength increases, combined with a model for strain hardening, are used to make predictions of the different effects of irradiation by the two particles on the entire flow curve that agree well with data

[en] A detailed description is presented of the technology of semifinished product manufacture for the A-1 reactor pressure vessel, with a view to heat treatment. The results of some metallographic and tensile strength tests are indicated. (Z.M.)

[en] The results are briefly discussed of radiation stability tests of the CSN 13030 steel. Changes are given in tensile strength, and curves are shown of notch toughness prior to and after neutron irradiation. The effects are also discussed of the method of deoxidizing, the type of heat treatment, and of chemical composition on radiation stability. (Z.M.)

No abstract available

[en] Tank 23 was placed in service in April 1964 receiving contaminated water from Buildings 244-H, the Receiving Basin for Off-Site Fuel (RBOF), and 245-H, the Resin Regeneration Facility (RRF). Tank 23 also provided emergency storage space for 500,000 gallons in the event of a severe contamination incident in Building 244-H. The tank has remained in this service since that time. The Tank 23 waste was processed initially by the 242-H evaporator, but since mid-1966 the waste has been processed through a zeolite bed to remove ¹³⁷C and other radioisotopes by ion exchange, and discarded to seepage basins. Inspections of the tank interior were made by using a 40-ft optical periscope and the thickness of the steel bottom of the tank was measured ultrasonically. Samples of the waste in the tank and liquid collected in the side wall and bottom sumps were analyzed. Several equipment modifications and repairs were made

No abstract available

[en] A survey is made of radiation effects information generated on the first four correlation-monitor materials provided by ASTM to radiation research and reactor surveillance programs. The survey was performed for Subcommittee 2 of ASTM Committee E-10 on Radiation Effects and includes a review of the worldwide distribution and use of the reference materials since 1960. The reference plates were those originally donated to ASTM by the U. S. Steel Corp. Individual plates are identified as 6 in. A302-B steel, 4 in. A212-B steel, 3 in. Ni-Cr-Mo (HY-80) steel and 2 in. T-1 steel. The report presents extensive tabulations of data as provided by the recipient laboratories. In addition, trends in radiation effects behavior with respect to tensile properties, Charpy-V notch ductility properties and postirradiation annealing response are identified and discussed. Nilductility transition (NDT) temperature behavior and dynamic tear (DT) test performance relative to notch ductility behavior are also identified for the A302-B and A212-B reference plates. The report is intended as a reference document for the evaluation and analysis of data developed by on-going reactor vessel surveillance programs and a source for data and data trends by which to assess the performance of new structural steels and to compare the effects of diverse reactor environments