SPERT III REACTOR FACILITY
Abstract
The Special Power Excursion Reactor Test III (Spert III) reactor is a pressurized-water nuclear-research reactor which was constructed to provide a facility for conducting reactor kinetic behavior and safety investigations. The investigations are designed to provide information for the advancement of pressurized-water and boiling-water reactor technology and safety. The facility was designed for operations up to pressures of 2500 psig and temperatures of 670 deg F and incorporates essential features typical of pressurized-water and boiling-water reactors. The engineering features of the reactor and supporting process equipment as constructed at the National Reactor Testing Station are described. (auth)
- Authors:
- Publication Date:
- Research Org.:
- Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
- OSTI Identifier:
- 4826907
- Report Number(s):
- IDO-16721
- NSA Number:
- NSA-16-003830
- DOE Contract Number:
- AT(10-1)-205
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTOR TECHNOLOGY; BOILING; CONFIGURATION; CONTROL SYSTEMS; EFFICIENCY; EXCURSIONS; FABRICATION; HEAT TRANSFER; HIGH TEMPERATURE; MATERIALS TESTING; MEASURED VALUES; MECHANICAL STRUCTURES; NEUTRON FLUX; PLANNING; PRESSURE; REACTIVITY; REACTOR SAFETY; REACTORS; RESEARCH REACTORS; SPERT-3; STABILITY; TEMPERATURE; TESTING; TRANSIENTS; VARIATIONS; WATER COOLANT
Citation Formats
Heffner, R.E., and Wilson, T.R. SPERT III REACTOR FACILITY. United States: N. p., 1961.
Web. doi:10.2172/4826907.
Heffner, R.E., & Wilson, T.R. SPERT III REACTOR FACILITY. United States. doi:10.2172/4826907.
Heffner, R.E., and Wilson, T.R. Wed .
"SPERT III REACTOR FACILITY". United States.
doi:10.2172/4826907. https://www.osti.gov/servlets/purl/4826907.
@article{osti_4826907,
title = {SPERT III REACTOR FACILITY},
author = {Heffner, R.E. and Wilson, T.R.},
abstractNote = {The Special Power Excursion Reactor Test III (Spert III) reactor is a pressurized-water nuclear-research reactor which was constructed to provide a facility for conducting reactor kinetic behavior and safety investigations. The investigations are designed to provide information for the advancement of pressurized-water and boiling-water reactor technology and safety. The facility was designed for operations up to pressures of 2500 psig and temperatures of 670 deg F and incorporates essential features typical of pressurized-water and boiling-water reactors. The engineering features of the reactor and supporting process equipment as constructed at the National Reactor Testing Station are described. (auth)},
doi = {10.2172/4826907},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Oct 25 00:00:00 EDT 1961},
month = {Wed Oct 25 00:00:00 EDT 1961}
}
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HEAT GENERATION WITHIN THE THERMAL SHIELDS AND VESSEL WALL OF THE SPERT-III REACTOR
Calculations of heat generation within the thermal shields and the vessel wall of the SPERT-III Reactor are presented. The calculations were performed to check an earlier estimate and assure adequacy of the shield design prior to installation in the reactor. The data are derived from an evaluation of the heat generated by the adsorption of gamma photons from fission and from neutron capture within the core, reflector and shield regions. The results predict that there will be no excessive thermal stresses within the shields and the vessel shell and that, therefore, the present SPERT-III thermal shield configuration is an adequatemore » -
SUMMARY OF THE SPERT-I, -II, AND -III REACTOR FACILITIES
A brief description and design data summary of each of operating, and physics data are tabulated for use as basic references. (auth)