1.-186. (canceled)
187. A system comprising:
for a nuclear fission traveling wave burnfront propagating along first and second dimensions, first electrical circuitry configured to determine a desired shape of the nuclear fission traveling wave burnfront along the second dimension within a plurality of nuclear fission fuel subassemblies according to a selected set of dimensional constraints;
second electrical circuitry configured to determine a migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner responsive to the desired shape; and
a subassembly configured to migrate selected ones of the plurality of nuclear fission fuel subassemblies responsive to the second electrical circuitry.
188. The system of claim 187, wherein the second electrical circuitry is further configured to determine an existing shape of the nuclear fission traveling wave burnfront.
189. The system of claim 187, wherein the second electrical circuitry is further configured to determine a migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner to establish the desired shape.
190. The system of claim 187, wherein the second electrical circuitry is further configured to determine a migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner to maintain the desired shape.
191. The system of claim 187, wherein the second electrical circuitry is further configured to determine a time when to migrate the selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner responsive to the desired shape.
192. The system of claim 187, wherein the plurality of nuclear fission fuel subassemblies are elongate along the second dimension.
193. The system of claim 187, wherein the first dimension is substantially orthogonal to an elongated axis of the plurality of nuclear fission subassemblies.
194. The system of claim 187, wherein the first dimension and the second dimension are substantially orthogonal to each other.
195. The system of claim 187, wherein:
the first dimension includes a radial dimension; and
the second dimension includes an axial dimension.
196. The system of claim 187, wherein:
the first dimension includes an axial dimension; and
the second dimension includes a radial dimension.
197. The system of claim 187, wherein:
the first dimension includes an axial dimension; and
the second dimension includes a lateral dimension.
198. The system of claim 187, wherein:
the first dimension includes a lateral dimension; and
the second dimension includes an axial dimension.
199. The system of claim 187, wherein:
the first locations include outward locations; and
the second locations include inward locations.
200. The system of claim 199, wherein the inward locations and outward locations are based on geometrical proximity to a central portion of the reactor core.
201. The system of claim 199, wherein the inward locations and the outward locations are based on neutron flux such that neutron flux at the inward locations is greater than neutron flux at the outward locations.
202. The system of claim 199, wherein the inward locations and the outward locations are based on reactivity such that keffective at the inward locations is greater than keffective at the outward locations.
203. The system of claim 187, wherein:
the first locations include inward locations; and
the second locations include outward locations.
204. The system of claim 203, wherein the inward locations and outward locations are based on geometrical proximity to a central portion of the reactor core.
205. The system of claim 203, wherein the inward locations and the outward locations are based on neutron flux such that neutron flux at the inward locations is greater than neutron flux at the outward locations.
206. The system of claim 203, wherein the inward locations and the outward locations are based on reactivity such that keffective at the inward locations is greater than keffective at the outward locations.
207. The system of claim 187, wherein the first locations and the second locations are located on opposite sides of a reference value along the first dimension.
208. The system of claim 187, wherein the first locations and the second locations include at least one attribute that is substantially equalized.
209. The system of claim 208, wherein the at least one attribute includes an attribute chosen from geometrical proximity to a central region of the reactor core, neutron flux, and reactivity.
210. (canceled)
211. (canceled)
212. The system of claim 187, wherein the second electrical circuitry is further configured to determine rotation of at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
213. The system of claim 187, wherein the second electrical circuitry is further configured to determine inversion of at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
214. The system of claim 187, wherein the subassembly includes a nuclear fuel handling apparatus.
215. The system of claim 187, wherein the subassembly is further configured to radially migrate selected ones of the plurality of nuclear fission fuel subassemblies from respective first locations toward respective second locations.
216. The system of claim 187, wherein the subassembly is further configured to spirally migrate selected ones of the plurality of nuclear fission fuel subassemblies from respective first locations toward respective second locations.
217. The system of claim 187, wherein the subassembly is further configured to axially translate selected ones of the plurality of nuclear fission fuel subassemblies.
218. The system of claim 187, wherein the subassembly is further configured to rotate selected ones of the plurality of nuclear fission fuel subassemblies.
219. The system of claim 187, wherein the subassembly is further configured to invert selected ones of the plurality of nuclear fission fuel subassemblies.
220. A nuclear fission traveling wave reactor comprising:
a nuclear fission traveling wave reactor core;
a plurality of nuclear fission fuel subassemblies received in the nuclear fission traveling wave reactor core, each of the plurality of nuclear fission fuel subassemblies being configured to propagate a nuclear fission traveling wave burnfront therein along first and second dimensions;
first electrical circuitry configured to determine a desired shape of the nuclear fission traveling wave burnfront along the second dimension within a plurality of nuclear fission fuel subassemblies according to a selected set of dimensional constraints;
second electrical circuitry configured to determine a migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner responsive to the desired shape; and
a subassembly configured to migrate selected ones of the plurality of nuclear fission fuel subassemblies responsive to the second electrical circuitry.
221. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine an existing shape of the nuclear fission traveling wave burnfront.
222. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine a migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner to establish the desired shape.
223. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine a migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner to maintain the desired shape.
224. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine a time when to migrate the selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations in a manner responsive to the desired shape.
225. The reactor of claim 220, wherein the plurality of nuclear fission fuel subassemblies are elongate along the second dimension.
226. The reactor of claim 220, wherein the first dimension is substantially orthogonal to an elongated axis of the plurality of nuclear fission subassemblies.
227. The reactor of claim 220, wherein the first dimension and the second dimension are substantially orthogonal to each other.
228. The reactor of claim 220, wherein:
the first dimension includes a radial dimension; and
the second dimension includes an axial dimension.
229. The reactor of claim 220, wherein:
the first dimension includes an axial dimension; and
the second dimension includes a radial dimension.
230. The reactor of claim 220, wherein:
the first dimension includes an axial dimension; and
the second dimension includes a lateral dimension.
231. The reactor of claim 220, wherein:
the first dimension includes a lateral dimension; and
the second dimension includes an axial dimension.
232. The reactor of claim 220, wherein:
the first locations include outward locations; and
the second locations include inward locations.
233. The reactor of claim 232, wherein the inward locations and outward locations are based on geometrical proximity to a central portion of the reactor core.
234. The reactor of claim 232, wherein the inward locations and the outward locations are based on neutron flux such that neutron flux at the inward locations is greater than neutron flux at the outward locations.
235. The reactor of claim 232, wherein the inward locations and the outward locations are based on reactivity such that keffective at the inward locations is greater than keffective at the outward locations.
236. The reactor of claim 220, wherein:
the first locations include inward locations; and
the second locations include outward locations.
237. The reactor of claim 236, wherein the inward locations and outward locations are based on geometrical proximity to a central portion of the reactor core.
238. The reactor of claim 236, wherein the inward locations and the outward locations are based on neutron flux such that neutron flux at the inward locations is greater than neutron flux at the outward locations.
239. The reactor of claim 236, wherein the inward locations and the outward locations are based on reactivity such that keffective at the inward locations is greater than keffective at the outward locations.
240. The reactor of claim 220, wherein the first locations and the second locations are located on opposite sides of a reference value along the first dimension.
241. The reactor of claim 220, wherein the first locations and the second locations include at least one attribute that is substantially equalized.
242. The reactor of claim 241, wherein the at least one attribute includes an attribute chosen from geometrical proximity to a central region of the reactor core, neutron flux, and reactivity.
243. (canceled)
244. (canceled)
245. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine rotation of at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
246. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine inversion of at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
247. The reactor of claim 220, wherein the selected set of dimensional constraints includes a predetermined maximum distance along the second dimension.
248. The reactor of claim 220, wherein the selected set of dimensional constraints is a function of at least one burnfront criteria.
249. The reactor of claim 248, wherein the burnfront criteria includes neutron flux.
250. The reactor of claim 249, wherein the neutron flux is associated with at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
251. The reactor of claim 248, wherein the burnfront criteria includes neutron fluence.
252. The reactor of claim 251, wherein the neutron fluence is associated with at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
253. The reactor of claim 248, wherein the burnfront criteria includes burnup.
254. The reactor of claim 253, wherein the burnup is associated with at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
255. The reactor of claim 248, wherein the burnfront criteria includes burnfront location within at least one of the selected ones of the plurality of nuclear fission fuel subassemblies.
256. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine a radial migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations.
257. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine a spiral migration of selected ones of the plurality of nuclear fission fuel subassemblies along the first dimension from respective first locations toward respective second locations.
258. The reactor of claim 220, wherein the second electrical circuitry is further configured to determine an axial translation of selected ones of the plurality of nuclear fission fuel subassemblies.
259. The reactor of claim 220, wherein the desired shape includes a shape chosen from a substantially spherical shape of the nuclear fission traveling wave burnfront, a shape conforming to a selected continuously curved surface, a shape that is substantially rotationally symmetrical around the second dimension, and a shape having substantial n-fold rotational symmetry around the second dimension.
260. (canceled)
261. (canceled)
262. (canceled)
263. The reactor of claim 220, wherein the desired shape of the nuclear fission traveling wave burnfront is asymmetrical.
264. The reactor of claim 263, wherein the desired shape of the nuclear fission traveling wave burnfront is rotationally asymmetrical around the second dimension.
265. The reactor of claim 220, wherein the subassembly includes a nuclear fuel handling apparatus.
266. The reactor of claim 220, wherein the subassembly is further configured to radially migrate selected ones of the plurality of nuclear fission fuel subassemblies from respective first locations toward respective second locations.
267. The reactor of claim 220, wherein the subassembly is further configured to spirally migrate selected ones of the plurality of nuclear fission fuel subassemblies from respective first locations toward respective second locations.
268. The reactor of claim 220, wherein the subassembly is further configured to axially translate selected ones of the plurality of nuclear fission fuel subassemblies.
269. The reactor of claim 220, wherein the subassembly is further configured to rotate selected ones of the plurality of nuclear fission fuel subassemblies.
270. The reactor of claim 220, wherein the subassembly is further configured to invert selected ones of the plurality of nuclear fission fuel subassemblies.
271.-306. (canceled)
The claims below are in addition to those above.
All refrences to claim(s) which appear below refer to the numbering after this setence.
1. A method for managing power of a mobile communication device that accesses data to a remote server through an internet, the method comprising the steps of:
(a) setting up a wake up time;
(b) checking a power supply status of the mobile communication device during the wake up time, and setting up the power supply status as an initial status;
(c) waking up the mobile communication device as un unattended mode, if the initial status is a suspended mode or an off mode, or taking the step (d), if the initial status is an on mode;
(d) connecting to the remote server and accessing data to the remote server, wherein the step (d) of accessing data includes the steps of
(d1) judging if the remote server has the data,
(d2) accessing data to the remote server, if the remote server has the new data, or taking the step (d3), if the remote server does not have the new data, and
(d3) stopping the connection between the mobile communication device and the remote server;
(e) renewing the wake up time; and
(f) shifting the power supply status of the mobile communication device into the initial status, and repeating the step (b).
2. The method according to claim 1, wherein in the step (d3), after stopping the connection with the remote server, if there are new data, then preset signals set up by the user are triggered.
3. The method according to claim 1, wherein the step (e) further comprises the steps of: judging if the power supply status of the mobile communication device is in the on mode; and taking the step (b), if the power supply status is in the on mode, or taking the step (f), if the power supply status is not in the on mode.
4. The method according to claim 1, wherein the wake up time in the step (a) is set up in a wake up module.
5. The method according to claim 4, wherein the wake up module in the on mode, the unattended mode, the suspended mode, and the off mode is always in an on status.
6. The method according to claim 1, wherein the wake up module sends a wake up signal to trigger a CPU in the mobile communication device for checking the power supply status.
7. The method according to claim 6, wherein in the step (c), the CPU renews the wake up time in the wake up module.
8. The method according to claim 6, wherein when the CPU is in the suspended mode, then the CPU is in a sleep status.
9. The method according to claim 6, wherein when the CPU is in the unattended mode, then a working voltage and clock frequency of the CPU are lower than those of the CPU in the on mode in order to reduce a power consumption.
10. The method according to claim 1, wherein the mobile communication device further comprises a wireless communication unit, and the step (d) uses the wireless communication unit to establish a connection with the remote server.
11. The method according to claim 10, wherein the mobile communication device further comprises a power management module for dynamically adjusting, according to required intensity of emitting power of radio wave and required bandwidth of data packet, a voltage of the wireless communication unit.
12. The method according to claim 10, wherein the wireless communication unit includes a communication module and a network module, and the wireless communication unit is connected to the remote server through the communication module and the network module.
13. The method according to claim 12, wherein in the step (d), connection with the remote server comprises the steps of:
(d1) judging if the communication module and the network module are switched on;
(d2) switching on at least one of the communication module and the network module and connecting to the internet, if the communication module and the network module both are not switched on; and
(d3) establishing the connection with the remote server through the internet.
14. The method according to claim 13, wherein in the step (d1), if the communication module and the network module both are switched on, then take the steps of:
(d11) judging if the mobile communication device is connected to the internet; and
(d12) connecting to the internet, if not connected to the internet, and establishing the connection with the remote server through the internet.
15. The method according to claim 14, wherein in the step (d11), if already connected to the internet, then the connection with the remote server is established through the internet.
16. The method according to claim 12, wherein the communication module connects the mobile communication device to the internet according to a GSMGPRS or GSM3G.
17. The method according to claim 12, wherein the communication module connects the mobile communication device to the internet through a wireless network technology.
18. The method according to claim 1, wherein the data are e-mails.
19. The method according to claim 1, wherein transmission of the data is transmitted according to a TCPIP protocol and in a TCP packet format or UDP packet format.