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Acceptance-test specifications for Test Number Four: process sensor and display test. [LMFBR]

Description: This document provides the general instructions for performing acceptance Test Number Four as indicated in the Acceptance Test Index (TI-022-130-003). Also indicated are the plant conditions and special equipment required to conduct the test. The acceptance criteria for each portion of the test are specified.
Date: May 9, 1975
Creator: Bell, C.R.
Partner: UNT Libraries Government Documents Department

Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Description: Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date: December 9, 1963
Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
Partner: UNT Libraries Government Documents Department

Sodium oxide aerosol study: NSPP runs 101 to 105, data record report. [LMFBR]

Description: This data record report summarizes the first five sodium oxide aerosol tests conducted in the Nuclear Safety Pilot Plant (NSPP) project at Oak Ridge National Laboratory. The goal of the project is to establish the validity (or level of conservatism) of the aerosol behavioral code, HAARM-2, and follow-on codes under development at the Battelle Columbus Laboratories for the U.S. Nuclear Regulatory Commission (NRC). Included in the report are descriptions of the five tests together with graphs and tables summarizing the results.
Date: March 9, 1978
Creator: Adams, R.E.; Kress, T.S. & Parsly, L.F. Jr.
Partner: UNT Libraries Government Documents Department

Mechanical properties of transient-tested irradiated fast-reactor cladding. [811/sup 0/ to 1644/sup 0/K; 5. 8 x 10/sup 22/ n/cm/sup 2/]

Description: Results are presented for three high burnup PNL-11 fuel pins irradiated to goal FFTF exposure levels in testing cladding stress and strain on fast reactor fuel pins subjected to simulated power transient conditions. The mixed oxide fuel with Type 316 SS clad were tested at heating rates of 5.5 k/s and 200 k/s with internal gas pressures of 17.2 to 98.6 MPa. Mechanical property data were obtained. Under short-term transient heating, neutron volumetric swelling does not change. Cladding strength does not exhibit a continuous degradation with increased neutron fluence, but does show saturation behavior or slight increase at higher fluences. (FS)
Date: August 9, 1978
Creator: Johnson, G. D. & Hunter, C. W.
Partner: UNT Libraries Government Documents Department

JUPITER-II Program: ANL analysis of ZPPR-13A and ZPPR-13B

Description: The ZPPR-13 experiments provide basic physics data for radial-heterogeneous LMFBR cores of approximately 700 MWe size. Assemblies ZPPR-13A, ZPPR-13B and ZPPR-13C comprised the JUPITER-II cooperative program between US-DOE and PNC of Japan. The measurements were made between August 1982 and April 1984. This report describes in detail the results of the ANL analyses of phases 13A and 13B/1 and includes preliminary results for the later assemblies of phase 13B. The data were compiled primarily for discussions at the Third Jupiter Analysis Meeting to be held at ANL-West between September 11th and 14th, 1984.
Date: August 9, 1984
Creator: Collins, P.J. & Brumbach, S.B. (comps.)
Partner: UNT Libraries Government Documents Department

Notes on the inherently safe core design meeting with the DOE-RRT, AI, GE, W-ARD, EPRI, and ETEC (at AI, Canoga Park, California, November 7-8, 1978). [LMFBR]

Description: The primary purpose of the meeting was to familiarize large LMFBR design managers with the capabilities of the Inherent Secondary Shutdown Systems (articulated rod and absorber balls) and to obtain inputs from them. The other purpose of the meeting was for the ISSS designers (AI, GE, and WARD) to present current work status, future plans, and schedules for their respective ISSS tasks.
Date: November 9, 1978
Creator: Jackola, A.S. & Paschall, R.K.
Partner: UNT Libraries Government Documents Department

Advanced multi-dimensional method for structural and hydrodynamic analyses of LMFBR piping systems

Description: Maintaining the structural integrity of the piping system of Liquid Metal Fast Breeder Reactors (LMFBRs) is essential to the safe operation of the reactor and steam supply systems. In the safety analysis various transient loads can be imposed on the piping systems, which may pose threats to the integrity of the piping structure. These transient loads can be classified into two categories. The first represents dynamic loads resulting from the hydrodynamic pressure-wave propagation or seismic events. The second represents static or quasi-dynamic loads generated by thermal wave propagation, normal operation transient, or creep phenomena. At Argonne National Laboratory, a multi-dimensional method has been developed for the integrated analysis of piping systems under these transient loading conditions. It utilizes a 2-D implicit finite-difference hydrodynamics in conjunction with a 3-D explicit finite-element structural analysis.
Date: April 9, 1985
Creator: Wang, C.Y. & Zeuch, W.R.
Partner: UNT Libraries Government Documents Department

EM 0211: standpipe-bubbler pump level control study, cover gas system analysis, (TASK B), W. P. 7373. [LMFBR]

Description: In addition to the basic definition of the Standpipe Bubbler performance, several tasks pertaining to specific cover gas/pump interface design problems were included within the Standpipe Bubbler Study effort. This report covers the following noted specific tasks of the Standpipe Bubbler Study: gas supply system design; gas ingestion by pump; identification of failure modes and recovery methods; manual override system; and effect of loss of gas pressure.
Date: August 9, 1976
Creator: Greer, A.
Partner: UNT Libraries Government Documents Department