CORCON-MOD1 preliminary evaluation and application to safety analysis of a large LMFBR plant

doi:10.2172/5274920

Preliminary design: duplex tube low-pressure saturated steam generator for large LMFBR plant. Final report

Dawson, B.E. October 1979

A preliminary design was completed for a steam generator which is applicable to a four loop LMFBR plant of 1000 MWe gross output employing dry and saturated steam conditions. Two steam generators of 364 MWt thermal capacity would be in each loop. The steam generator is a straight, duplex tube design with a shell bellows for thermal expansion and a single tubesheet with an integral leak detection system. The report outlines a proposed series of development tasks to provide additional design data for the duplex tube and to demonstrate the steam generator design with test modules. The design can bemore »« less
Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR]

Cowan, C.L. ; Protsik, R. ; Lewellen, J.W. January 1984

The Large Core Code Evaluation Working Group Benchmark Problem Four was specified to provide a stringent test of the current methods which are used in the nuclear design and analyses process. The benchmark specifications provided a base for performing detailed burnup calculations over the first two irradiation cycles for a large heterogeneous fast reactor. Particular emphasis was placed on the techniques for modeling the three-dimensional benchmark geometry, and sensitivity studies were carried out to determine the performance parameter sensitivities to changes in the neutronics and burnup specifications. The results of the Benchmark Four calculations indicated that a linked RZ-XY (Hex)more »« less
DOI: 10.2172/6931395

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INDIAN POINT NUCLEAR GENERATING UNIT NO. 2. PRELIMINARY SAFETY ANALYSIS REPORT. PLANT DESIGN DESCRIPTION AND SAFETY ANALYSIS

None January 1965
BROOKWOOD NUCLEAR STATION UNIT NO. 1. PRELIMINARY FACILITY DESCRIPTION AND SAFETY ANALYSIS REPORT. Plant Design Description and Safety Analysis

None October 1966
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2. PRELIMINARY SAFETY ANALYSIS REPORT. PLANT DESIGN DESCRIPTION AND SAFETY ANALYSIS

None January 1965

Title: CORCON-MOD1 preliminary evaluation and application to safety analysis of a large LMFBR plant

Abstract

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Preliminary design: duplex tube low-pressure saturated steam generator for large LMFBR plant. Final report

Large Core Code Evaluation Working Group Benchmark Problem Four: neutronics and burnup analysis of a large heterogeneous fast reactor. Part 1. Analysis of benchmark results. [LMFBR]

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2. PRELIMINARY SAFETY ANALYSIS REPORT. PLANT DESIGN DESCRIPTION AND SAFETY ANALYSIS

BROOKWOOD NUCLEAR STATION UNIT NO. 1. PRELIMINARY FACILITY DESCRIPTION AND SAFETY ANALYSIS REPORT. Plant Design Description and Safety Analysis

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2. PRELIMINARY SAFETY ANALYSIS REPORT. PLANT DESIGN DESCRIPTION AND SAFETY ANALYSIS