Big Chemical Encyclopedia

Chemical substances, components, reactions, process design ...

Articles Figures Tables About

Critical assembly

A critical assembly is a split bed on which fissionable material used to mock up up a separated reactor core that is stacked half on each half. One half is on roller guides so that the two halves may be quickly pulled apart if the neutron multiplication gets too high. Use the Preliminary Hazards Analysis method described in section 3,2.1 to identify the possible accidents that may occur and the qualitative probabilities and consequences. List the initiators in a matrix to systematically investigate the whole process. Don t forget human error. [Pg.243]

A critical assembly is a split bed on which fissionable material used to mockup up a... [Pg.501]

Technician fails to follow procedures Should have no consequences Low Critical Assembly is designeii to fail safe. [Pg.502]

Crow, M. M., and Bozeman, B. (1998). Limited by Design R D Laboratories in the LLS. National Innovation System. New York Columbia University Press. Hoddeson, L., et al. (1993). Critical Assembly A Technical History of Los Alamos Dining the Oppenheimer Years, 1943-1945. New York Cambridge University Press. [Pg.820]

Storage must prevent a critical assembly being formed under any condition. [Pg.58]

Approximately 180 research reactors and critical assemblies currently are under IAEA safeguards. The vast majority of the research reactors operate at relatively low power levels (10 megawatts-thermal or lower) and the critical assemblies at virtually zero power. [Pg.567]

Nuclear reactors, including critical and sub-critical assemblies, reactor equipment and materials. Reactor systems, sub-systems, equipment and components... [Pg.591]

Experimental Reactors and Critical Assemblies Fission products, neutrons, fissile and fissionable material, transuranics Up to tens of TBq Various areas, up to square kilometers in the case of widespread contamination. [Pg.68]

Nuclear Safety. The increased use of enriched uranium in nuclear fuel has meant that the designer of the materials processing plant has had to accept a further constraint that no quantity of uranic material capable of forming a critical assembly will be present in any section of the plant and that an accidental accumulation of such a mass inside or outside of the plant is not possible. This may be achieved by ... [Pg.341]

In the case of an interacting array of identical units, MONK will automatically calculate the number of unit lattice cells which form a critical assembly from the results of a calculation relating to one unit cell. This is made possible since all that is required are the numbers of neutrons entering and leaving each face of the unit cell, and these are stored during the boundary tracking. This method is known as the PQR method (14). [Pg.95]

Measurements of Reactor Parameters in Subcritical and Critical Assemblies Irving Kaplan... [Pg.369]

This Safety Guide covers regulatory inspection and enforcement in relation to nuclear facihties such as enrichment and fuel manufacturing plants nuclear power plants other reactors such as research reactors and critical assemblies spent fuel reprocessing plants and facilities for radioactive waste management, such as... [Pg.11]

A2.1.1 Experimental Pacilitiee. Some extensive changes were made in the physical arrangement of the equipment described in Appendix 1 which in> creased safety, ease of operation, and control of the critical assembly. The general arrangement is sketched in Fig. A2.A. Not shown is an exit from the control room to the outside as an emergency exit and security gate. [Pg.422]

Effect of Experimental Holes in the High-flux Ucactor Critical Assemblies... [Pg.448]

Buenos Aires Critical Assembly, Argentina, 1983 Vandellos NPP, Spain, 1989... [Pg.206]

Figure 3 The Slowpoke reactor a view of the critical assembly and reactor container, lower section. (Reprinted with permission from Atomic Energy of Canada Limited (AECL) Research, Canada.)... Figure 3 The Slowpoke reactor a view of the critical assembly and reactor container, lower section. (Reprinted with permission from Atomic Energy of Canada Limited (AECL) Research, Canada.)...
The final stage was devoted to the measurements of the control rod worth and sodium void reactivity effect in the core sector including all three different enrichment zones (BFS-58-4 critical assembly was simulating the reactor at the beginning of the run after refueling). [Pg.156]

BFS-1 critical facility was used to continue studies on the characteristics of fast reactor cores designed for the weapons grade plutonium utilization and minor actinides burning, for instance, the effect of neptunium introduction into fuel. The first stage of these studies made on the insert of the BN-800-Superphenix reactor fuel with up to 14% of depleted uranium dioxide replaced by neptunium dioxide was accomplished in 1995 (BFS-67 critical assemblies set). [Pg.156]

In the second half of 1996, BFS-71-1 critical assembly was mounted with MOX fuel containing about 55% of plutonium. Standard measurements were carried out, and neptunium was added to the fiiel in the late 1996 in order to continue measurements. The results obtained are under analysis. [Pg.157]

In 1996, all scheduled studies on the uranium-thorium fuel cycle were completed on the CBR-22 critical assembly with the core containing metal enriched uranium and metallic thorium. The high enrichment of the core fuel ( 20%) caused quite rigid neutron spectrum (neutron fraction having energy lower than 10 KeV did not exceed 1%). [Pg.157]

A series of tests were also carried out on the CBR-22 critical assembly on the substantiation of changing over fi om the fertile blanket to the steel blanket, the radioactive isotopes to be yielded in the latter. The replacement of uranium blanket by the steel one has resulted in significant reactivity gain (up to 0.9% Akcfp ff). [Pg.158]

As a very rough estimate, a marine PWR core will reach the end of its useful life once about 40% of the fuel has been used, after which point it must be refuelled. For a core with a fuel load of SO kg of this equates to 30 kg remaining. This end of life fuel load gives an indication of how much fuel is required for a critical assembly of a lattice of fuel pins in water. Hence, for all core types, in the following analysis a mass of fuel of less than 30 kg will be considered to be unable to achieve criticality, while a mass of more than that may achieve it. [Pg.68]

The icebreaker PWR used UOj fuel with a BCR of 0.0011 mm a . However, Container C contained only 60% or 20.6 kg of the total fuel from the N2 reactor which is assumed here to be too low an amount for a critical assembly to form. [Pg.69]


See other pages where Critical assembly is mentioned: [Pg.495]    [Pg.502]    [Pg.502]    [Pg.538]    [Pg.9]    [Pg.925]    [Pg.50]    [Pg.1603]    [Pg.581]    [Pg.925]    [Pg.345]    [Pg.51]    [Pg.7070]    [Pg.226]    [Pg.541]    [Pg.578]    [Pg.610]    [Pg.612]    [Pg.612]    [Pg.432]    [Pg.447]    [Pg.32]    [Pg.38]    [Pg.61]    [Pg.69]    [Pg.70]   
See also in sourсe #XX -- [ Pg.191 , Pg.267 ]




SEARCH



Critical assembly concentration

Critical micelle concentration , molecular self-assembly

Critical self-assembly concentration

Critical zero power--------assembly

Introduction to surfactants - basic properties, self-assembly and critical packing parameter (CPP)

© 2024 chempedia.info