Claims |
Self-sustained fissioning of uranium-238 can be accomplished via steam- moderated neutrons |
---|---|
Related disciplines | |
Year proposed | 1998 |
Proponents | Claudio Filippone |
The Clean and Environmentally Safe Advanced Reactor (CAESAR) is a
nuclear reactor concept created by Claudio Filippone, the Director of the Center for Advanced Energy Concepts at the
University of Maryland, College Park and head of the ongoing CAESAR Project. The concept's key element is the use of
steam as a
moderator, making it a type of
reduced moderation water reactor. Because the
density of steam may be controlled very precisely, Filippone claims it can be used to fine-tune
neutron fluxes to ensure that
neutrons are moving with an optimal energy profile to split
238
92U
nuclei – in other words, cause
fission.
The CAESAR reactor design exploits the fact that the
fission products and
daughter isotopes produced via nuclear reactions also decay to produce additional
delayed neutrons. Filippone claims that unlike light water-cooled fission reactors, where fission occurring in
enriched
235
U
fuel rods moderated by liquid-water
coolant ultimately creates a
Maxwellian
thermal neutron flux profile, the neutron energy profile from delayed neutrons varies widely. In a conventional reactor, he theorizes, the moderator slows these neutrons down so that they cannot contribute to the 238
U
reaction; 238
U
has a comparatively large cross-section for neutrons at high energies.
Filippone maintains that when steam is used as the moderator, the average neutron energy is increased from that of a liquid water-moderated reactor such that the delayed neutrons persist until they hit another nucleus. The resulting extremely high
neutron economy, he claims, will make it possible to maintain a
self-sustaining reaction in fuel rods of pure 238
U
, once the reactor has been started by enriched fuel.
Skeptics[
who?]
, however point out that it is generally believed that a controlled, sustained chain reaction is not possible with 238
U
. Starting in the 1930s Physicists have used the
Six factor formula and its derivative
Four factor formula to calculate the behavior of nuclear chain reactions inside a mass of fissile material.
[1] Based on these calculations even an infinitely large mass of pure U-238 is incapable of sustaining a chain reaction with only its own neutron production, so coupling the gas-cooled fast-spectrum core with a moderated outer slow-neutron section is required, or alternatively some level of fissile enrichment is required.
[2] It can undergo fission when impacted by an energetic neutron with over 1
MeV of
kinetic energy. But the high-energy neutrons produced by 238
U
fission (after quickly losing energy by inelastic scattering), are not, themselves, sufficient to induce enough successive fissions in 238
U
to create a critical system (one in which the number of neutrons created by fission is equal to the number absorbed). Instead, bombarding 238
U
with neutrons below the 1 MeV fission threshold causes it to absorb them without fissioning (becoming 239
U
) and decay by
beta emission to
239
Pu
(which is itself
fissile).
[3] The energy of
delayed neutrons is so low that contribution to 238
U
fission is almost 0.0000, requiring some fissile material to keep the reactor safely under
prompt criticality: (e.g. 235
U
in natural
uranium and preferably also some moderator, possibly outside the extra-fast core).
The maximum ratio of 238
U
fission is limited by the neutron physics to less than 100%, but greater than 40%, which allows even a relatively low conversion ratio of 0.6 to breed its own fuel (without uranium enrichment or Pu produced elsewhere). Conversion ratio of 0.6 is achievable in practice (actually achieved even with light-water reactor designs that waste a lot of neutrons in Boron, that has better alternatives).
Claims |
Self-sustained fissioning of uranium-238 can be accomplished via steam- moderated neutrons |
---|---|
Related disciplines | |
Year proposed | 1998 |
Proponents | Claudio Filippone |
The Clean and Environmentally Safe Advanced Reactor (CAESAR) is a
nuclear reactor concept created by Claudio Filippone, the Director of the Center for Advanced Energy Concepts at the
University of Maryland, College Park and head of the ongoing CAESAR Project. The concept's key element is the use of
steam as a
moderator, making it a type of
reduced moderation water reactor. Because the
density of steam may be controlled very precisely, Filippone claims it can be used to fine-tune
neutron fluxes to ensure that
neutrons are moving with an optimal energy profile to split
238
92U
nuclei – in other words, cause
fission.
The CAESAR reactor design exploits the fact that the
fission products and
daughter isotopes produced via nuclear reactions also decay to produce additional
delayed neutrons. Filippone claims that unlike light water-cooled fission reactors, where fission occurring in
enriched
235
U
fuel rods moderated by liquid-water
coolant ultimately creates a
Maxwellian
thermal neutron flux profile, the neutron energy profile from delayed neutrons varies widely. In a conventional reactor, he theorizes, the moderator slows these neutrons down so that they cannot contribute to the 238
U
reaction; 238
U
has a comparatively large cross-section for neutrons at high energies.
Filippone maintains that when steam is used as the moderator, the average neutron energy is increased from that of a liquid water-moderated reactor such that the delayed neutrons persist until they hit another nucleus. The resulting extremely high
neutron economy, he claims, will make it possible to maintain a
self-sustaining reaction in fuel rods of pure 238
U
, once the reactor has been started by enriched fuel.
Skeptics[
who?]
, however point out that it is generally believed that a controlled, sustained chain reaction is not possible with 238
U
. Starting in the 1930s Physicists have used the
Six factor formula and its derivative
Four factor formula to calculate the behavior of nuclear chain reactions inside a mass of fissile material.
[1] Based on these calculations even an infinitely large mass of pure U-238 is incapable of sustaining a chain reaction with only its own neutron production, so coupling the gas-cooled fast-spectrum core with a moderated outer slow-neutron section is required, or alternatively some level of fissile enrichment is required.
[2] It can undergo fission when impacted by an energetic neutron with over 1
MeV of
kinetic energy. But the high-energy neutrons produced by 238
U
fission (after quickly losing energy by inelastic scattering), are not, themselves, sufficient to induce enough successive fissions in 238
U
to create a critical system (one in which the number of neutrons created by fission is equal to the number absorbed). Instead, bombarding 238
U
with neutrons below the 1 MeV fission threshold causes it to absorb them without fissioning (becoming 239
U
) and decay by
beta emission to
239
Pu
(which is itself
fissile).
[3] The energy of
delayed neutrons is so low that contribution to 238
U
fission is almost 0.0000, requiring some fissile material to keep the reactor safely under
prompt criticality: (e.g. 235
U
in natural
uranium and preferably also some moderator, possibly outside the extra-fast core).
The maximum ratio of 238
U
fission is limited by the neutron physics to less than 100%, but greater than 40%, which allows even a relatively low conversion ratio of 0.6 to breed its own fuel (without uranium enrichment or Pu produced elsewhere). Conversion ratio of 0.6 is achievable in practice (actually achieved even with light-water reactor designs that waste a lot of neutrons in Boron, that has better alternatives).