摘要:
The oscillatory forces acting on an eccentric rod within a diffuser are reduced by an annular bypass collar around the rod immediately upstream of the diffuser region. The collar includes a sleeve portion that completely surrounds the rod and a bypass channel outside the sleeve which carries most of the fluid into the diffuser region on a path parallel to but spaced from the rod. The collar is most effective when a multiplicity of discrete bypass channels are provided.
摘要:
A new part length rod is provided which may be used to not only control xenon induced power oscillations but also to contribute to shutdown reactivity when a rapid shutdown of the reactor is required. The part length rod consists of a control rod with three regions. The lower control region is a longer weaker active portion separated from an upper stronger shorter poison section by an intermediate section which is a relative non-absorber of neutrons. The combination of the longer weaker control section with the upper high worth poison section permits the part length rod of this invention to be scrammed into the core. When a reactor shutdown is required but also permits the control rod to be used as a tool to control power distribution in both the axial and radial directions during normal operation.
摘要:
An apparatus for the safe storage of a plurality of fissionable masses including an array of discrete neutron absorbing shields which utilizes the principle of the neutron trap to reduce the multipication factor of the storage array to a subcritical value when immersed in a neutron moderating medium. Each discrete neutron absorbing shield is designed to perimetrically encircle each of the stored fissionable masses. Each shield is spaced such that the encircled fissionable mass is spaced from the next adjacent neutron absorbing shield by a distance determined by the enrichment of the fissionable masses and attenuation of the moderating medium.
摘要:
An enclosed reservoir is sized and located in relation to the steam generator of a pressurized water nuclear reactor power plant so that upon a loss of feedwater flow to the steam generator, a gravity induced supplementary flow into the steam generator is automatically initiated to dissipate the residual heat generated in the reactor. The height of the reservoir is the same as the distance between upper and lower design limits on steam generator feedwater level. The top of the steam generator is fluidly connected to the top of the reservoir to equalize the pressure therebetween. The gravity induced flow from the reservoir to the steam generator produces a water level in the steam generator that stays within the upper and lower design limits.
摘要:
A method and apparatus for the storage of fuel in a stainless steel egg crate structure within a storage pool. Fuel is initially stored in a checkerboard pattern or in each opening if the fuel is of low enrichment. Additional fuel (or fuel of higher enrichment) is later stored by adding stainless steel angled plates within each opening, thereby forming flux traps between the openings. Still higher enrichment fuel is later stored by adding poison plates either with or without the stainless steel angles.
摘要:
A new part length rod is provided which may be used to not only control xenon induced power oscillations but also to contribute to shutdown reactivity when a rapid shutdown of the reactor is required. The part length rod consists of a control rod with three regions. The lower control region is a longer weaker active portion separated from an upper stronger shorter poison section by an intermediate section which is a relative non-absorber of neutrons. The combination of the longer weaker control section with the upper high worth poison section permits the part length rod of this invention to be scrammed into the core. When a reactor shutdown is required but also permits the control rod to be used as a tool to control power distribution in both the axial and radial directions during normal operation.
摘要:
An apparatus for the safe storage of a plurality of fissionable masses including an array of discrete neutron absorbing shields which utilizes the principle of the neutron trap to reduce the multiplication factor of the storage array to a subcritical value when immersed in a neutron moderating medium. Each discrete neutron absorbing shield is spaced such that the encircled fissionable mass is spaced from the next adjacent neutron absorbing shield by a distance determined by the enrichment of the fissonable masses and attenuation of the moderating medium.
摘要:
A method and apparatus for increasing the reliability of linear drive devices of a nuclear reactor to scram the control elements held in a raised position thereby. Each of the plurality of linear drive devices includes a first type of holding means associated with the drive means of the linear drive device and a second type of holding means distinct and operatively dissimilar from the first type. The system of linear drive devices having both types of holding means are operated in such a manner that the control elements of a portion of the linear drive devices are only held in a raised position by the first holding means and the control elements of the remaining portion of linear drive devices are held in a raised position by only the second type of holding means. Since the two types of holding means are distinct from one another and are operatively dissimilar, the probability of failure of both systems to scram as a result of common mode failure will be minimized. Means may be provided to positively detect disengagement of the first type of holding means and engagement of the second type of holding means for those linear drive devices being operative to hold the control elements in a raised position with the second type of holding means.
摘要:
A liquid level sensing apparatus (32) senses the level of liquid surrounding the apparatus. A plurality of axially spaced sensors (36) are enclosed in a separator tube (86). The separator tube (86) tends to collapse the level of a two-phase fluid within the separator tube into essentially a liquid phase and a gaseous phase where the collapsed level bears a relationship to the coolant inventory outside the separator tube. The level of the liquid phase is sensed by level sensing apparatus (32). The separator tube (86) contains inlet-outlet ports (90,92) near the top and bottom thereof to equalize the liquid level inside and outside the separator tube (86) when the level fluctuates or the water within the separator tube (86) flashes to steam. Each sensor (36) is comprised of a heater (64), a heated thermocouple junction (68) and an unheated thermocouple junction (66) within an elongated heat conductive housing (62). The heated portion of housing (62) is enclosed in a splash guard (72) with inlet-outlet ports ( 78,82) near the top and bottom to equalize the liquid level inside and outside the splash guard (72) and to eliminate the spurious indications of liquid level change which may arise if water droplets contact the housing (62) in the region of the heater. To prevent steam bubbles entrained in a two-phase fluid cross flow from entering the lateral inlet-outlet ports (90,92) of the separator tube (86), the separator tube (86) is enclosed in support tube (100) which may in turn be enclosed in an otherwise unused control element assembly shroud (110). The lateral inlet-outlet ports (90,92) of separator tube (86) are axially offset from lateral inlet-outlet ports (102) of support tube 100 at least where support tube 100 is subjected to cross flow. The shroud (110) is open on the bottom and has lateral inlet-outlet ports (112) to facilitate liquid level fluctuations to equalize inside and outside shroud (110). An alternate embodiment permits the measurement of more than one liquid level.