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This report addresses details of the Advanced SR-90 Space Power Supply Study

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Comparisons of the experimental data on seal pressure distributions obtained from the A-11 Flow Induced Vibration Test, Phases I and III, with analytical results including porous flow through the unimpregnated inner reflector cylinder for the same operating conditions show generally very good agreement. The principal deviations between analysis and experiment occurs when high pressure ratios exist across the last seal. Additional investigation, both in the relationship used in the analytical model and in the experimental area, are required to determine the cause of the deviation found between analysis and experiment when the pressure ratio across the last seal is near critical. As a result of this comparison, it appears that the analytical methods and assumtions made in predicting unheated seal pressure distributions are resonable, and may be used with confidence in the test prediction of the NRX-A1 cold flow test.

This report presents the design significance of the test results and their application to actual reactor operation. In so doing, it complies with the NRX-A2 component test analysis requirements.

The interface seal between the inner reflector cylinder and the nozzle flange prevents coolant flow from bypassing the reflector system and core and flowing directly from the reflector inlet plenum to the core exit.

This report analyzes the available B-3, single seal, high pressure, isothermal test data in compliance with the NRX-A1 Cold Flow Test pre-requisite requirements.

This book is intended as a laboratory reference tool. The separate book chapters have been written by workers in the various fields covered, with a couple written by the contributing editor, Clement J. Rodden. The chapters were abstracted separately for the database.

Detailed results of the parameter studies are presented. The analog simulation is described and discussed, including the analytical model and analog circuits used.

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The purpose of the study was to provide a comparison of the characteristics of a space power system operating on the Brayton cycle with either neon or argon.

The capability of calculating the close-in effects of the shock wave from an underground nuclear explosion has been demonstrated. Agreement was obtained between calculation and measurements using a spherically symmetric, hydrodynamic, elastic-plastic code called SCC for the Hardhat event, a 5-kiloton nuclear detonation in granite. This capability is dependent upon having a more or less complete description of the elastic and dynamic properties of the materials involved. When this information is available, agreement within the limits of uncertainty of the measurements can be calculated for peak pressures, peak particle velocities, shock wave time of arrival, and pressure pulse shapes. (auth)

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Comparison of analytical and experimental flow induced core vibrations has been made for all applicable tests performed to date. These include the KIWI B-4A and B-4B reactors, the KIWI PIE tests and the A-11 component tests. It can be concluded that the analog and experimental results are in good agreement. Similar calculations on the NRX-A reactor design indicate that vibrations will not occur.

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