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Master--slave manipulators and remote maintenance at the Oak Ridge National Laboratory

Description: The volume of master-slave manipulator maintenance at Oak Ridge National Laboratory has necessitated the establishment of a repair facility and the organization of a specially trained group of craftsmen. Emphasis on cell containment requires the use of manipulator boots and the development of precise procedures for accomplishing the maintenance of 283 installed units. To provide the most economical type of preventive maintenance, a very satisfactory computer- programmed maintenance system has been established at the Laboratory. (auth)
Date: January 1, 1975
Creator: Jenness, R.G. & Wicker, C.D.
Partner: UNT Libraries Government Documents Department

Comments on the use of the Monte Carlo method for criticality calculations

Description: As evidenced by recent papers given at Nuclear Criticality Safety Division meetings, the use of the Monte Carlo method has become a very popular computational tool. The ease of use has undoubtably been a primary reason for this popularity. This ease of use, however, may lead to a false sense of security when using the method. Guidance on the effective use of the method and some suggestions on how to avoid some of the pitfalls that can occur are presented. (TFD)
Date: January 1, 1975
Creator: Whitesides, G.E.
Partner: UNT Libraries Government Documents Department

Subcritical mass limits for the T-insert

Description: Safe limits are derived for Class III shipments of $sup 235$U, $sup 239$Pu, and $sup 233$U in the T-insert within the ANL T-2 cask. The cask has a 6.063-in.-dia cavity enclosed by lead 8 in. thick and clad with steel. The insert is 5-in. Schedule 40 stainless steel. No control is exercised over the configuration of the fissile material. The most restrictive of the conditions that must be satisfied for a Class III shipment is the requirement that the cask be subcritical when flooded internally and externally with water. Mass limits for the cask were calculated by ANISN with S$sub 4$ quadrature. Hansen-Roach cross sections were used, supplemented by some with the same group structure from other sources. To establish the bias in the method, calculations of k/sub eff/ were compared with appropriate critical experiments with aqueous solutions of $sup 233$U, $sup 235$U, and Pu and with HFIR experiments in which the core was reflected by steel, lead, and water. (TFD)
Date: January 1, 1975
Creator: Clark, H.K.
Partner: UNT Libraries Government Documents Department

Spent fuel shipping, reprocessing, and recycle fabrication in the HTGR fuel cycle

Description: From joint power generation conference; New Orleans, Louasiana, USA (16 Sep 1973). The High Temperature Gas Cooled Reactor (HTGR) fuel recycle operation is described. The description includes the HTGR spent fuel shipping system and the proposed method of reprocessing the spent fuel to recover the bred /sup 233/U and /sup 235/U. The process for refabricating the recovered fuel into recycle fuel is also discussed. (auth)
Date: December 15, 1972
Creator: Brooks, L.H.; Davis, C.R.; Peterman, D.D. & Spaeth, M.E.
Partner: UNT Libraries Government Documents Department

Remote maintenance experience in the Transuranium Processing Plant at ORNL

Description: From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA (11 Nov 1973). Special features to permit remote maintenance and replacement of equipment were incorporated into the Transuranium Processing Plant during initial design in 1962. However, these features were not required initially and were first tested during the summer of 1972. Until then, radiation levels were sufficiently low to permit most maintenance operations to be performed directly by men wearing air suits. Radiation levels increased during 1971 and 1972 due to a processing program for the recovery of large quantities of curium and californium from targets that had been very highly irradiated. These increased levels of both gamma and neutron radiation backgrounds dictated the shielding of equipment in tank pits by- water flooding and required that maintenance be done from above through a shield as a routine procedure in most of the plant. Of eight tools developed for remote maintenance, four were demonstrated during the actual maintenance program to be completely adequate; three required slight modification or were rebuilt to make them more versatile or to make them stronger. One tool required complete redesign to fulfill needs demonstrated during the maintenance work. Experience during 1972 showed that the original design concept of ten years ago has resulted in a very successful operating facility from the standpoint of flexibility and maintainability. A short period of maintenance activities during 1973 demonstrated the adequacy of the tools that were developed for remote maintenance. (auth)
Date: January 1, 1973
Creator: Peishel, F.L.; Evans, W.W. & Matherne, J.L.
Partner: UNT Libraries Government Documents Department

Fission gas and void volume measuring system

Description: From joint meeting of the American Nuclear Society and the Atomic lndustrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA (11 Nov 1973). A system which provides a measurement of the amount of gas and free void volume contained in encapsulated fuel elements has been in use at LASL for over a year. A gas sample which can be used for mass analysis is also obtained from this system. Using this equipment, the quantity of gas moles released is obtained to better than plus or minus 2% and the void volume is determined to better than plus or minus (2 cc + 3% of void volume). (auth)
Date: April 30, 1974
Creator: Lazarus, M.E.
Partner: UNT Libraries Government Documents Department