Organic Moderated Reactor Experiment
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| Status | Decommissioned |
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The Organic Moderated Reactor Experiment (OMRE) was a 16 MWt experimental organic nuclear reactor that operated at the National Reactor Testing Station from 1957 to 1963 to explore the use of hydrocarbons as coolant, moderator, and reflector materials in power reactor conditions[1]. Such organic fluids are non-corrosive, do not become highly activated under irradiation, and can operate at low pressure and moderate temperature. These characteristics were considered promising towards the goal of achieving economical commercial nuclear power.
Design
[edit]
The OMRE design efforts began in July 1955[2]. It was originally intended to operate for 1 year[3]
The objectives of the OMRE program were to obtain the following experimental information[3]: 9 :
- Rate of radiation and thermal damage to the hydrocarbon in the reactor
- Effect of this damage upon the operation of the reactor
- Suitable methods for ensuring satisfactory reactor operation in the presence of damaged hydrocarbon
It was neither a pilot plant nor a prototype, but rather a minimum-cost experimental facility designed to investigate the feasibility of the organic concept to power reactors.
The system was designed with diphenyl in mind, with flexibility to try other polyphenyls.
The design criteria stated included:
- Maximum fuel surface temperature between 750 °F and 800 °F
- Bulk coolant temperature between 500 °F and 700 °F
- Coolant velocity in fuel plats up to 15 ft/s
- Heat rejection capacity of 16 MWt
- Average thermal neutron flux in fuel of 2e13 n/cm^2/s
It used a UO2-stainless steel plate type fuel enriched to 93% with 3 mil thick stainless steel cladding. It did not have a power conversion system.
It had a 14-foot deep pool of hydrocarbons for upper shielding, with a nitrogen cover gas pressurized to 200 psig. The nitrogen was continuously purged from the system to sweep out any hydrogen from decomposition of the coolant-moderator and discharge it out the stack.
Coolant was pumped at 9,200 gpm through an air-blast heat exchanger to dump the core heat to the atmosphere. A steam system and power conversion system were not used to simplify the construction and operation of the reactor experiment.
At high temperature and under irradiation, the hydrocarbons decompose and form longer chains with increasing molecular weight. This gradually degrades the heat transfer and flow characteristics of the fluid. To mitigate this, a coolant-moderator purification ran continuously to remove any hydrocarbons that had been damaged by heat or radiation. This was accomplished with a low-pressure distillation system.
All systems were constructed with carbon steel, except the reactor vessel. All systems had heaters (including induction heating, trace heat, and an oil-fired heater on the air-blast heat exchangers) to bring the system above the melting temperature of the coolant-moderator.
Construction
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Construction of OMRE began on June 17th 1956 and completed in May 1957[2]. The reactor consists of a concrete pad and corrugated steel cylinder surrounded by compacted earth for radiation shielding.
Clearing, grading, roads, walks, drainage, water supply, power substation, sanitary and process waste systems, fencing, security lighting, guard station, communications system, control and processing building, and reactor foundation excavation were performed in Phase I of the construction by the Idaho Operations Office and the Atomic Energy Commission.[4]. Some delays were encountered due to appropriations delays and a steel strike.
The biggest setback was unsatisfactory performance of the control-rod drive mechanism. During testing, it became apparent that the original design would not work, and a new approach was needed.
Process piping was constructed of Schedule 40 carbon steel.
The buildings and utilities were constructed by Wadsworth & Arrington.
Operation
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The OMRE first achieved criticality on September 17, 1957, and reached full power at the beginning of February, 1958.[1] The reactor operated in two modes: without the purification system, and with the purification system. Seventeen tests were run with the first OMRE core throughout 1958 with reactor power between 0 and 12 MWt.
The first three tests were system check-out tests, covering all major systems. Subsequent tests simulated the conditions expected to be encountered in the Piqua Nuclear Generating Station. Test 4 demonstrated that pyrolitic decomposition rate in external piping was negligible. Tests 5-11 measured the decomposition rate and the effect of radiation damage on coolant-moderator heat-transfer characteristics. Tests 12 and 13 tested the purification system's ability to reduce the concentration of inorganic particulate matter while also reducing the high-boiler concentration from 40% to 8%.[1]
Three fuel element failures occurred during first core operation. Two occurred in experimental low-enriched assemblies with finned aluminum cladding due to inadequate coolant filtration, and the third was caused by improper element seating.[1]
By the end of the first year, the core had generated 958 MW-day of energy and been in operation for 5,600 hours. An extended shutdown followed to replace the core.[1]
Decommissioning
[edit]Immediately following final OMRE shutdown, the nuclear fuel and reactor vessel internals were removed, and the organic coolant was drained from all the systems.
The facility was eventually decontaminated and decommissioned between October 1977 and September 1979[5]. The process was complicated by the existence of some remaining toxic and flammable Santowax R and xylene, a neutron-activated radioactive vessel emitting 350 R/h, and asbestos insulation. Furthermore, due to insufficient neutron shielding being included in the design, "an extraordinary, unexpected amount of activated rock and soil was removed.[5]: ii
The surface radiation of the excavation and backfill material was brougt to 20 R/hr or less, and the nuclide content of the backfill soil was brought below 0.5 pCi/g.
The decommissioning effort was initially estimated to cost $700,000 and take 2 years, and was completed on time and under budget, for a total cost of $500,000.[5]: 15
References
[edit]- ^ a b c d e Trilling (1959-11-01). "OMRE OPERATING EXPERIENCE". Nucleonics. 17 (11): 113–117. Retrieved 12 December 2024.
- ^ a b CIVILIAN POWER REACTOR PROGRAM. PART III. BOOK 7. STATUS REPORT ON ORGANIC-COOLED POWER REACTORS AS OF 1959. Atomic Energy Commission, Washington, D.C.; Atomics International. Div. of North American Aviation Inc., Canoga Park, Calif. 1960-01-01. p. 44. Retrieved 2024-12-11.
- ^ a b Sletten, H. L. (1958-02-01). Organic Moderated Reactor Experiment Safeguards Summary (Report). North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div. Retrieved 2024-12-13.
- ^ U.S. Atomic Energy Commission; North American Aviation (1957). Proceedings of the SRE-OMRE forum held at Los Angeles, California, November 8 and 9, 1956. TID-7525. Oak Ridge, Tennessee: United States Atomic Energy Commission, Technical Information Service Extension. Retrieved 2024-12-13.
- ^ a b c Hine, R. E. (1980-09-01). Decontamination and decommissioning of the Organic Moderated Reactor Experiment facility (OMRE) (Report). United States.
