The Heavy Water Components Test Reactor and the Heavy Water Power Reactor Program

A 1962 film about the US effort to develop natural-uranium heavy water power reactors

By Nick Touran, Ph.D., P.E., 2025-02-10 , Reading time: 18 minutes

In 1956, the US Atomic Energy Commission commissioned a study on the development of heavy-water moderated natural uranium fueled power reactors with the objective of producing low-cost commercial electricity. Since these reactors do not require any enrichment, it was thought that they could be cost competitive with fossil fuel power plants. To obtain more credible data, the Heavy Water Components Test Reactor (HWCTR) was built. This film describes the Heavy Water program and the HWCTR.

The Savannah River Site was already making 1000 tons of heavy water/year for the weapons program and had dropped the cost from $70/lb to $28/lb. At these rates, it was conceivable to make cheap power plants.

Catalog description: This film depicts the growing need for nuclear power and describes the features of heavy water reactors for use in power production. The development program conducted by the Atomic Energy Commission on this reactor concept is described in detail. Design studies performed on promising heavy water reactor concepts established the technical feasibility and economic promise of this concept. A number of research tasks in the fields of fuel design, engineering of low leakage components, studies of heat transfer and the physics of natural uranium heavy water systems were investigated in detail by Dupont and other research contractors to the USAEC. The facilities at the Savannah River Laboratory and at commercial laboratories used in this program are shown. Primary emphasis in the development program was placed on design of an inexpensive natural uranium fuel element for the heavy water reactor. Processes of fuel fabrication of both uranium metal and uranium oxide are described. To verify the results of the fuel development and other engineering programs a test reactor called a Heavy Water Components Test Reactor (HWCTR) was constructed at the Savannah River Plant. The film describes the construction of this reactor and outlines in detail the technical features and capabilities of the HWCTR and its special loop systems in demonstrating the heavy water reactor concept.

This is film 88394 in our catalog.

A very special thanks to Nuclear Talent Scout for sponsoring the digitization of this amazing film.
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Stills from the film

Title card Title card
Reactor under construction Reactor under construction
Control room Control room
Sign for Parr, SC reactor Sign for Parr, SC reactor
Reactor diagram Reactor diagram
Barrels of U3O8 yellowcake Barrels of U3O8 yellowcake
Heavy water Heavy water
Savannah River facilities Savannah River facilities
More Savannah River More Savannah River
Heavy water production facilities could produce 1000 tons per year Heavy water production facilities could produce 1000 tons per year
Heavy water production facilities Heavy water production facilities
Heavy water being transferred Heavy water being transferred
Tanks of heavy water Tanks of heavy water
A control system A control system
Old data tapes Old data tapes
Study showing 100 MWe was too small Study showing 100 MWe was too small
Bigger is better Bigger is better
Graphic of the HWCTR Graphic of the HWCTR
Reactor designer in bowtie Reactor designer in bowtie
Equipment clearing land for construction Equipment clearing land for construction
A boiling heavy water direct cycle pressure tube reactor A boiling heavy water direct cycle pressure tube reactor
Process Development Pile being used for lattice studies Process Development Pile being used for lattice studies
Assemblies in a stainless steel tank that an hold 100 tons of heavy water Assemblies in a stainless steel tank that an hold 100 tons of heavy water
High temperature and pressure non-nuclear studies on lattices High temperature and pressure non-nuclear studies on lattices
Computer studies were performed Computer studies were performed
Nuclear Metals Incorporated co-extruding tubular uranium metal fuel elements Nuclear Metals Incorporated co-extruding tubular uranium metal fuel elements
Fabrication techniques were studied systematically Fabrication techniques were studied systematically
Test fuel was irradiated in Vallecitos BWR Test fuel was irradiated in Vallecitos BWR
Fuel was also irradiated in the E20 loop at NRU in Canada Fuel was also irradiated in the E20 loop at NRU in Canada
Hot cell studies and post irradiation examination at SRS Hot cell studies and post irradiation examination at SRS
A tubular fuel element in the hot cell A tubular fuel element in the hot cell
Natural uranium UO2 powder Natural uranium UO2 powder
UO2 fuel pellets would work but were expensive UO2 fuel pellets would work but were expensive
Assembling a bundle of UO2 fuel with zircaloy cladding Assembling a bundle of UO2 fuel with zircaloy cladding
Fuel elements manufactured for testing in HWCTR Fuel elements manufactured for testing in HWCTR
Leak testing of heavy water components is essential Leak testing of heavy water components is essential
Corrosion and vibration test rig Corrosion and vibration test rig
Observing corrosion from the test Observing corrosion from the test
Non-nuclear heat transfer studies to estimate burnout Non-nuclear heat transfer studies to estimate burnout
The monolithic slab of concrete for the HWCTR foundation The monolithic slab of concrete for the HWCTR foundation
Biological shielding and spent fuel basin. The shielding was 11 feet thick Biological shielding and spent fuel basin. The shielding was 11 feet thick
The reactor building used reinforced concrete below grade and a reinforced shell above grade The reactor building used reinforced concrete below grade and a reinforced shell above grade
Containment steel dome designed for 29 psig Containment steel dome designed for 29 psig
The completed reactor dome The completed reactor dome
Pump development at Bingham Pump Company in Portland, OR Pump development at Bingham Pump Company in Portland, OR
Reactor vessel fabrication at Pacific Coast Engineering Co in San Francisco Reactor vessel fabrication at Pacific Coast Engineering Co in San Francisco
Reactor weighed 98 tons and made of carbon steel Reactor weighed 98 tons and made of carbon steel
All inside surfaces were clad with 304 stainless steel All inside surfaces were clad with 304 stainless steel
Reactor vessel being shipped Reactor vessel being shipped
Reactor vessel can handle 1500 psi at 600 degrees F Reactor vessel can handle 1500 psi at 600 degrees F
Reactor vessel being lifted Reactor vessel being lifted
Vessel being shipped by rail Vessel being shipped by rail
Vessel being shipped by rail Vessel being shipped by rail
Installing the vessel in the reactor building Installing the vessel in the reactor building
Illustration of tubular fuel with coolant on both sides Illustration of tubular fuel with coolant on both sides
Illustration of double tubular fuel elements with three coolant regions Illustration of double tubular fuel elements with three coolant regions
Clusters of UO2 rods Clusters of UO2 rods
Control rod drives and head of the HWCTR on movable platform that swings to the side Control rod drives and head of the HWCTR on movable platform that swings to the side
Fuel handling equipment for the HWCTR Fuel handling equipment for the HWCTR
Guy running the fuel handling machine of the reactor Guy running the fuel handling machine of the reactor
Chain in fuel handling machine Chain in fuel handling machine
Fuel element coming out during handling Fuel element coming out during handling
Core map with driver fuel on the outside and test positions on the inside Core map with driver fuel on the outside and test positions on the inside
There were two isolated coolant loops of the reentrant type in the 6 outer test positions There were two isolated coolant loops of the reentrant type in the 6 outer test positions
Main reactor coolant system Main reactor coolant system
Control room of HWCTR Control room of HWCTR
Another control room view Another control room view
Adjusting control rods Adjusting control rods
Health physics room Health physics room
Air lock Air lock
Other equipment (filtering?) Other equipment (filtering?)
Aerial view of HWCTR Aerial view of HWCTR
The end The end

See Also

  • Austin, W., and D. Brinkley. “HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING.” Savannah River Site (SRS), Aiken, SC (United States), October 13, 2011. https://www.osti.gov/biblio/1027493.
  • “Heavy Water Components Test Reactor Decommissioning - Major Component Removal.” Savannah River Site (SRS), Aiken, SC (United States), May 5, 2010. https://www.osti.gov/biblio/978453.
  • Collins, James A., and Maxwell Gensamer. “Heavy Water Components Test Reactor: Condition of Reactor Vessel (Final Report).” Savannah River Site (SRS), Aiken, SC (United States), October 1, 1961. https://doi.org/10.2172/1891327.
  • Guay, A. E. “Behavior of Metallic-Uranium Tubular Fuel Elements during High Temperature Irradiation.” Douglas United Nuclear, Inc., Richland, Wash. (USA), June 13, 1969. https://www.osti.gov/biblio/5099594.
  • “HEAVY-WATER-MODERATED POWER REACTORS ENGINEERING AND ECONOMIC EVALUATIONS. VOLUME I. SUMMARY REPORT.” Du Pont de Nemours (E.I.) & Co. Engineering Dept., Winmington, Del., June 1, 1960. https://doi.org/10.2172/4133696.
  • “HEAVY-WATER-MODERATED POWER REACTORS ENGINEERING AND ECONOMIC EVALUATIONS. VOLUME II. ENGINEERING STUDIES AND TECHNICAL DATA.” Du Pont de Nemours (E.I.) & Co. Engineering Dept., Wilmington, Del., December 1, 1960. https://doi.org/10.2172/4068768.
  • Hood, R. R., and L. Isakoff. “Heavy Water Moderated Power Reactors. Progress Report for December 1959.” Du Pont de Nemours (E.I.) & Co. Atomic Energy Div., Wilmington, DE (United States); Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL), January 1, 1960. https://doi.org/10.2172/4182427.
  • Kiger, E. O. “OPERATIONAL SUMMARY OF THE HEAVY WATER COMPONENTS TEST REACTOR, OCTOBER 1961-DECEMBER 1964.” Du Pont de Nemours (E.I.) and Co., Aiken, S.C. Savannah River Lab., April 1, 1966. https://doi.org/10.2172/4541128.
  • “LARGE HEAVY-WATER-MODERATED POWER REACTORS. An Engineering Feasibility Study.” Du Pont de Nemours (E.I.); Co., Wilmington, Del., November 1, 1964. https://doi.org/10.2172/4676628.
  • Marshall, R. P. “ANALYSIS OF FAILED 17-4 PH BOLTS FROM THE HWCTR.” Du Pont de Nemours (E. I.) and Co., Aiken, S. C. Savannah River Lab., January 1, 1967. https://doi.org/10.2172/4503601.
  • McKibben, J. M. “CORROSION OF EQUIPMENT IN THE HEAVY WATER COMPONENTS TEST REACTOR.” Du Pont de Nemours (E.I.) and Co., Aiken, S.C. Savannah River Lab., June 1, 1965. https://doi.org/10.2172/4584728.
  • Quigley, H. C. “IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR.” Du Pont de Nemours (E.I.) & Co., Wilmington, Del., April 1, 1962. https://doi.org/10.2172/4818425.

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