ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT
You are accessing a document from the Department of Energy's (DOE) OSTI.GOV.
This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service.
Visit OSTI to utilize additional information resources in energy science and technology.
Abstract
UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a msximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas. (auth)
- Publication Date:
- Research Org.:
- Los Alamos Scientific Lab., N. Mex.
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 4792064
- Report Number(s):
- LA-2689
- NSA Number:
- NSA-16-015907
- DOE Contract Number:
- W-7405-ENG-36
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTOR TECHNOLOGY; ACCIDENTS; BUILDINGS; CERAMICS; CONTAMINATION; COOLANT LOOPS; ENVIRONMENT; FAILURES; FUEL ELEMENTS; GAS COOLANT; GRAPHITE MODERATOR; HELIUM; HIGH TEMPERATURE; MECHANICAL STRUCTURES; OPERATION; PERSONNEL; RADIATION DOSES; REACTOR SAFETY; REACTORS; UHTREX
Citation Formats
None. ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT. United States: N. p., 1962.
Web. doi:10.2172/4792064.
None. ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT. United States. doi:10.2172/4792064.
None. Thu .
"ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT". United States.
doi:10.2172/4792064. https://www.osti.gov/servlets/purl/4792064.
@article{osti_4792064,
title = {ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT},
author = {None},
abstractNote = {UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a msximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas. (auth)},
doi = {10.2172/4792064},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1962},
month = {3}
}