Vessel concrete containment

ASME Code Sec. Ill Nuclear Power Plant Components This section of the code includes vessels, storage tanks, and concrete containment vessels as well as other nonvesseJ items. 

Division 2 - Code for concrete reactor vessels and containments... 

A model of possible terrorist attack (single shot at metal-concrete container from grenade cup discharge at on-shore site of Atomflof , Mmmansk Shipping Company) was presented in the 2002 NATO-Russia Advanced Research Workshop Remaining Issues in the Decommissioning of Nuclear Powered Vessels [2]. According to the model, even such - not very powerfiil - hypothetical terrorist impact could lead to serious implications for personnel and environment. 

U.S. Nuclear Regulatory Commission. Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments). Regulatory Guide 1.142, Revision 1, Washington, DC, November 1981. 

Safety-related concrete structures for nuclear power plants (other than reactor vessels and containments) (DG-1098, Proposed revision 2, published 08/2000) (Rev.l, ML003740197 Rev.2, ML013100274) April 1978 (R l/10/1981, 2/11/2001). 

The goals of this development were (1) Enhanced safety and reliability, (2) Reduced occupational radiation exposure and radioactive waste, (3) Enhanced operability and maneuverability and (4) Improved economy. Significant improvements were induced by the adoption of the reactor internal pump, fine motion control rod drive mechanism, integral type reinforced concrete containment vessel and digital control system. Cross-section of reactor buildings for 1100MW(e)-class BWR and ABWR are described in Figure 2. 

A study of the effects of concrete and plastic enclosures around single and multiple vessel arrays containing enriched U02(N0s)2 solutions. The results of Uiese measurements will be valuable in determining the adequacy with which current criticality codes evaluate the neutron reflector properties of ccmcrete and plastic. 

NuScale power module reactor pressure vessel and containment vessel located within steel-lined concrete pool. 

I) Concrete containment 2) Containment steel shell 3) Polar crane 4) Reactor pressure vessel S) Control rod drive mechanism 6) Spent fuel pool 7) Refuelling machine 8) Steam generator 9) Pressurizer 10) Pressurizer relief tank 11) Main coolant pump 12) Main steam line 13) Feedwater line 14) Concrete shield IS) Accumulator 16) Personnel lock 17) Mate rials lock 18) Lifting gantry 19) Fresh fuel assembly storage 20) Borated water storage tank 21) Residual heat cooler 22) Component cooler 23) Safety injection pump (By courtesy of Siemens/KWU)... 

Shielding 1.91 cm thick mild steel pressure vessel in contained pit of 122 cm thick barvtes concrete... 

Boiler and pressure vessel code section III, division 2-subsection CB and CC concrete reactor vessels and containment Section XI boiler and pressure vessel code-fuels for inservice inspection of nuclear power plant components... 

TAN, C. A Study of the Design and Construction Practices of Prestressed and Reinforced Concrete Containment Vessels. The Franklin Institute Research Laboratories, Philadelphia, 1969, p. 506. 

Lorenz, H. Design of the concrete containment vessel for the R. E. Ginna nuclear power plant. Nuclear Engineering and Design Vol. 6,1967, pp. 360-366. 

ACI-ASME Technical Committee on Concrete Pressure Components for Nuclear Service. Proposed standard code for concrete reactor vessels and containments, copyright 1973. 

ACI-ASME Joint Technical Committee. Code for Concrete Reactor Vessels and Containments. ASME Boiler and Pressure Vessel Code Section in. Division 2 and AC I Standard 359-74, 1975. 

Kuroda et al. Recent advances in concrete containment vessels in Japan, Nuclear Engineering and Design, Vol. 140, 1993. 

Kuroda, Hasegawa. Recent topics on concrete containment vessels in Japan verification of SIT and assurance of safety margins, Japan. Proceedings of Seminar on Containment of Nuclear Reactors in conjunction with 5tii SMIRT, Seoul, 1999. 

Setogawa, Sakarai, Funokoshi, Yemaguchi, Koike, Kamei, and Hagro. Structural Integrity tests of prestressed concrete containment vessels at Ohi NPP, SMIRT 12, Vol H, 1993. 

Tamura, Watanabe, Kato, Yamaguchi, Koike, Komatsu. A delayed phenomena evaluation of prestressed concrete containment vessel at Tsuruga Unit 2 power station. SMIRT 11, 1991. 

Bangash, M.Y.H. The structural Integrity of concrete containment vessels under external impact. Proc. 6" Inter. Conf. Struc. Mech. React. Technology Paper J7/6, Paris, 1981. Bangash, M.Y.H. Reactor Pressure Vessel Design and Practice. Prog. Nucl. Energy, 10, 69-124, 1982... 

Buchert K. P. et al. (1978) Analysis of reinforced concrete containment vessels considering concrete cracking Nuclear Eng. Des. 46. 101-107. 

A Complete Manual Design Analysis of Concrete Containment Vessel (Building) Using American Practices and Codes... 

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