Prestressed Concrete Reactor Vessel Model 1 Page: 8
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4. To demonstrate that a PCRV with the required integrity can be
constructed using conventional techniques and typical construction
manpower. Since the experience on similar vessels had been
gained in Europe, reassurance was necessary that the construction
standards were achievable in the United States.
5. To obtain design data and to establish criteria for materials and
components that could be combined into a satisfactory vessel.
The prestres sing tendons with anchors which are normally used
for prestressed structures do not necessarily have the character-
istics most applicable for a PCRV. Also, further demonstration
was needed that concrete of sufficient strength and uniformity
could be placed in a structure containing the amount of reinforcing
steel and the number of prestressing tendons required for a PCRV.
6. To observe the structural response of the vessel and to determine
the strains within the reinforced concrete, the liner, and the pre-
stressing system under prestressing and pressure loads. The
response of the vessel to pressures in excess of the normal
working range was of particular interest.
7. To investigate the behavior of the vessel at ultimate strength.
1. 1.2. Approach
1. 1. 2. 1. PCRV Concept. The PCRV was selected, from several
concepts being considered, as the primary containment vessel for a
250-MW(e) version of the HTGR (Fig. 1. 2). For this version, the steam
generators and helium circulators were inside the PCRV, located in a
cylindrical annular space around the reactor. Steam and feedwater piping
penetrated the vertical walls of the cylinder. Reactor control rod drives
were top mounted and occupied top head penetrations, which also provided
access for refueling.
The penetration requirements were:
1. Thirty-seven control and refueling penetrations, 18 in. in diam,
located on an equilateral triangular pitch and immediately above
the reactor.
2. Three steam generator and circulator access penetrations, 7 ft
in diam.
3. Eight steam and feedwater penetrations, 18 in. in diam.8
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Prestressed Concrete Reactor Vessel Model 1, report, October 25, 1966; San Diego, California. (https://digital.library.unt.edu/ark:/67531/metadc304068/m1/20/: accessed April 24, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.