Plant design, nuclear

Lyczkowski, R.W. and Ching, J.T. (1979) Safety consideration and economic advantage of a new underground nuclear power plant design . Nuclear Eng. Design, 53, pp. 257-261. 

GALVIN, M., TODREAS, N.E., CONWAY, L.E., Maintenance cycle extension in the IRIS Advanced light water reactor plant design. Nuclear Technologies 143, 270-280. 

R. L. Loftness, Nuclear Power Plants Design, Operating Experience and Economics, D. Van Nostrand Co. Inc., Princeton, N.J., 1964. 

Two studies resolved the Unresolved Safety Issue A-44, "Station Blackout." The first siudy, The Reliability of Emergency AC Power Systems in Nuclear Power Plants," when combined uh die lelevant loss-oToffsite-power frequency, provides estimates of station-blackout frequencies lor 18 nuclear power plants and 10 generic designs. The study also identified the design and operational features most important to the reliability of AC power systems. The second study, "Station Blackout Accident Analysis" (NUREG/CR-3226), focused on the relative importance to risk of laiion blackout events and the plant design and operational features that would reduce this risk. 

Initiating events, in this study, initiate plant scram or setback. Other initiators, such as refueling discharge accidents, do not necessarily cause a reactor shutdown but may lead t< minor fuel damage and radioactive releases. The list of initiators for nuclear power plants has litf ance for HFBR because of size and design differences. A list of HFBR-specific initiators was developed from " st prepared with the HFBR staff, the FSAR, the plant design manual, the procedures manual, techn specifications, monthly operating reports, and the HFIR PRA (Johnson, 1988). 

Boric acid [B(OH)3] is employed in primary coolant systems as a soluble, core reactivity controlling agent (moderator). It has a high capture cross-section for neutrons and is typically present to the extent of perhaps 300 to 1,000 ppm (down from perhaps 500 to 2,500 ppm 25 years ago), depending on nuclear reactor plant design and the equilibrium concentration reached with lithium hydroxide. However, boric acid may be present to a maximum extent of 1,200 ppm product in hot power nuclear operations. 

The data on probabilities given in this example are for illustration only, and do not represent actual data for these components. Some quantitive data on the reliability of instruments and control systems is given by Lees (1976). Examples of the application of quantitive hazard analysis techniques in chemical plant design are given by Wells (1996) and Prugh (1980). Much of the work on the development of hazard analysis techniques, and the reliability of equipment, has been done in connection with the development of the nuclear energy programmes in the USA (USAEC, 1975) and the UK. 

An international nuclear safety organization could be set up to adopt world safety standards, and approve standardized plant designs which could be built efficiently in volume around the world. This international organization, or additional ones, could approve, or provide, standard operator and maintenance training and like the IAEA could provide periodic inspections to assure that safety standards are being maintained, and that nuclear materials were not being illegally diverted. Indeed, perhaps the IAEA could be expanded to meet these requirements. 

Defense-in-depth concept, for nuclear power plant design, 17 534-536 Defense Logistics Agency (DLA), 14 201 Defensins, 18 258-259... 

Nuclear Power Plant Design, Construction Maintenance... 

Nuclear Decommissioning Clean-Up Nuclear Fuel, Equipment Services Nuclear Fuel Disposal Recycling Transportation Services Nuclear Plant Design Services... 

Nuclear Power Plant Design Engineering Technology Training... 

Source Book, 4th ed., Nuclear Energy Institute, 1996 Soviet-Designed Nuclear Power Plant Profiles, US Department of Energy, 1999. 

Solar-nuclear hybrid variants of the HyS cycle process have also been investigated to explore potential synergies. Two hybrid plant designs were analysed ... 

Although the duration of construction was influenced by various factors, including the accident at Three Mile Island, economic conditions and power needs, the history and trend of extended times to obtain operating licenses was a motivation for the development of an alternate licensing process, which is defined in 10 CFR Part 52. The licensing process in 10 CFR Part 52 involves the possible submittal of a nuclear power plant design for certification and the approval of specific sites via an... 

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