GB2497756A - A process for the rapid shut-down of nuclear fission reactions - Google Patents
A process for the rapid shut-down of nuclear fission reactions Download PDFInfo
- Publication number
- GB2497756A GB2497756A GB1121843.5A GB201121843A GB2497756A GB 2497756 A GB2497756 A GB 2497756A GB 201121843 A GB201121843 A GB 201121843A GB 2497756 A GB2497756 A GB 2497756A
- Authority
- GB
- United Kingdom
- Prior art keywords
- text
- boron
- shut down
- proteus
- boron trioxide
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000006243 chemical reaction Methods 0.000 title claims abstract description 26
- 230000004992 fission Effects 0.000 title claims abstract description 22
- 238000000034 method Methods 0.000 title claims description 19
- 230000008569 process Effects 0.000 title claims description 16
- JKWMSGQKBLHBQQ-UHFFFAOYSA-N diboron trioxide Chemical compound O=BOB=O JKWMSGQKBLHBQQ-UHFFFAOYSA-N 0.000 claims abstract description 56
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims abstract description 14
- 238000010276 construction Methods 0.000 claims abstract description 9
- 239000000446 fuel Substances 0.000 claims abstract description 4
- 239000004327 boric acid Substances 0.000 claims description 15
- 241000588769 Proteus <enterobacteria> Species 0.000 claims description 9
- 230000007613 environmental effect Effects 0.000 claims description 7
- 230000004907 flux Effects 0.000 claims description 7
- 230000001629 suppression Effects 0.000 claims description 5
- 238000005516 engineering process Methods 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 238000004017 vitrification Methods 0.000 claims description 2
- 238000002485 combustion reaction Methods 0.000 claims 1
- 239000000356 contaminant Substances 0.000 claims 1
- 239000006185 dispersion Substances 0.000 claims 1
- 231100000572 poisoning Toxicity 0.000 claims 1
- 230000000607 poisoning effect Effects 0.000 claims 1
- 239000002574 poison Substances 0.000 abstract description 4
- 231100000614 poison Toxicity 0.000 abstract description 4
- 239000007788 liquid Substances 0.000 abstract description 2
- 238000012958 reprocessing Methods 0.000 abstract description 2
- 229960002645 boric acid Drugs 0.000 abstract 1
- 235000010338 boric acid Nutrition 0.000 abstract 1
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 1
- 229910052796 boron Inorganic materials 0.000 description 6
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 5
- 230000000694 effects Effects 0.000 description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 2
- 230000008901 benefit Effects 0.000 description 2
- 230000015556 catabolic process Effects 0.000 description 2
- 150000001875 compounds Chemical class 0.000 description 2
- 230000001419 dependent effect Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 239000001301 oxygen Substances 0.000 description 2
- 229910052760 oxygen Inorganic materials 0.000 description 2
- 231100000279 safety data Toxicity 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- OSWFIVFLDKOXQC-UHFFFAOYSA-N 4-(3-methoxyphenyl)aniline Chemical compound COC1=CC=CC(C=2C=CC(N)=CC=2)=C1 OSWFIVFLDKOXQC-UHFFFAOYSA-N 0.000 description 1
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 125000005619 boric acid group Chemical group 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 235000019253 formic acid Nutrition 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 239000005355 lead glass Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 238000005979 thermal decomposition reaction Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/22—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/24—Selection of substances for use as neutron-absorbing material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/033—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by an absorbent fluid
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Molten boron trioxide (B2O3) is introduced to a nuclear fission environment resulting in a neutron poison reaction and the eventual full shut down of an active nuclear fission reaction within a nuclear reactor pressure vessel, pressure chamber, or equivalent construction that may be subject to fission reaction events, such as a spent fuel pond or reprocessing facility. The boron trioxide may be added in a pre-melted liquid form, or derived from boric acid (H3BO3) introduced directly into the high temperature nuclear fission environment. The boron trioxide or boracic acid should be arranged to completely fill the reaction vessel or chamber so as to isolate and enclose any exposed or broken off fuel components, seal any breach in the vessel or chamber, and negate the possibility of any combustible gas ignition.
Description
Proteus Boron Shut Down Process Patent
DESCRIPTION.
1. Basic Principles and Process The Boron shut down process proposes that MOLTEN BORON TREOXIDE be used to precipitate the eventual full shut down of an active nuclear fission reaction, within a reactor pressure vessel, pressure chamber, or equivalent construction that may be subject to fission reaction cvents such as a spcnt ifiel pond or reprocessing facility.
The Boron Trioxide can be added be added pre-melted in liquid form, or Boric Acid (powder) may be added and this on being subject to the heat of a fission reaction will eventually evolve the required Boron Trioxide. In both cases the Boron will act as a neutron poison' and eventually facilitate a ceasing of fission reactions it is applied to.
2, Composition The base chemical requirement is Boric Acid (EI3BO3) in its pure form. It may be preheated to a minimum temperature of 500°C and this will evolve Boron Trioxide (B2O3) in its molten state. In both cases the maximum temperature at application and then usage should not be more than 1500°C, at which point thermal decomposition may lead to the breakdown of the compound and the production of pure Boron and gaseous Oxygen.
Note that the breakdown of the compound will not lower the effect of the Boron as a neutron poison, but the loss' of the Oxygen will reduce the overall volume with the application area and could lead to the re-exposure of fission source materials or elements.
3. Preparation Initially the active component Boric Acid will be retained in a bulk storage mechanism that would hold a minimum of 100% of the total internal volume of the vessel or chamber into which it is to be injected, and allow it to be heated on a continual basis to a minimum of 500°C for (eventual) molten application in the Boron Trioxide form. The mechanical means of the Boron Trioxide injection is not process critical, except in that it must provide for a complete injection whilst the said chemical is at its preferred operating temperature and its frilly molten state.
4. Initial Usage Regardless of whether Boric Acid or Boron Trioxide is applied, in both cases the application should be sufficient to completely fill the reactor pressure vessel, pressure chamber, or equivalent construction it is injected into. Once this is achieved the following beneficial effects in reference to the management and safety of that vessel or chamber...
4.1 By filling the vessel or chamber completely, flammable gasses such as hydrogen and their possible sources such as water or steam will be filly expelled. The effect of this will be to fully prevent gas or steam related ignitions or explosions within the chamber, vessel or construct. It should be noted that if the Boric Acid is applied directly, water and thus steam will evolve as it converts to Boron Trioxide and this water/steam will itself add to the ignition suppression capability of the process until the vessel or chamber is completely filled.
4.2 Should the chamber or vessel be breeched or holed, then the molten Boron Trioxide will by intent flow through such and then be subject to (normally or by operator interaction) a relatively cooler environment in comparison to that within the vessel or chamber. In this case the expelled' or external Boron Trioxide Flux' will cool at a faster rate, and when having lost its fluidity and cooled will start to back fill' and eventually plug or stop the breech to a lesser or greater extent 4.3 The Boron Trioxide Flux' will when the vessel or chamber is full, isolate any exposed nuclear fuel elements and act as suppressive agents to any ongoing fission reactions, and thus act as a neutron poison. The object of this sub-process is the eventual reaching of first a cool, and then a cold shut down (equivalent) of any ongoing fission reactions.
4.4 The Boron Trioxide Flux wifl when the vessel or chamber is ff11, act as an ongoing (in effect) flux based vitrification process until the shut downs listed in (3) above are achieved. The object of this sub-process is the collection and containment of any fuel or radiologically contaminated control elements within the vessel or chamber, that may have separated or broken away from their normal system position or ifinction position.
5. Subsequent Usage Over time, specifically dependent on the unknown' of the fission reaction source, an eventual cool shut down equivalent will be achieved. This phase will require that the vessel, chamber or construct remain completely full of the Boron Trioxide Flux' and that the volume be fully maintained should some new variable or circumstance lead otherwise. Once this phase is achieved then all active fission reactions should be negated and the lead glass itself may begin to cool at a rate determined by any residual radiological effects or reactions still extant.
Following this the normal standard cold' shut down procedures may bc initiated, dependent of course on the condition and safety of the vessel, chamber or construct to which the Boron Trioxide was applied.
6. Boron Shut Down Process Summary
This process facilitates an easily applied, but effective means of achieving a cool shut down equivalent on any applicable ongoing fission reaction environment or situation. It also offers significant benefits to the recovery of normal pertinent system management operations.
Finally it offers a safe path to an eventual full cold shut down equivalent and a safe containment environment that can if required be expanded upon for the benefit of local environmental circumstances.
7. Referetices and Sourccs http://emwikipcdiaorg/wiki/Boric acid -Boric Acid general properties.
http://cn.wilcipedia.org/wiki/Borontrioxide -Boron Trioxide genera/properties.
http:/'en.wikipedia.org/wiki'Neutron 0015011 -Neutron Poisvns general properties.
httwilen.wikinedia.org/wiki'uc1ear meltdown -Nuclear core damage.
http://en.wikipcdi&or/wiki/NucIear reactor technology -Fission reaction technology.
hp2ww.inchem.oscumcslls/icsc/icsc/eicQ99J2h1m -Boric Acid safety data.
h ____________ ____________ 303-862 -Boron Trioxicle safety data.
Claims (1)
- <claim-text>SCLAIMS.1. 1 claim that the Proteus Boron Shut Down Process, which comprises of the the addition or application of Boric Acid (evolving Boron Trioxide) or Boron Trioxide itself to an ongoing fission reaction environment, will provide neutron poisoning, and combustion suppression, eventually leading to a cool shut down or equivalent status within that environment.</claim-text> <claim-text>2. The Proteus Boron Shut Down Process recited in claimi, wherein the Boric Acid (evolving Boron Trioxide and Water) is applied to an ongoing fission reaction, will negate the possibility of combustible gas ignition.</claim-text> <claim-text>3. The Proteus Boron Shut Down Process recited in claiml, wherein the molten Boron Trioxide, either directly itself or having evolved from a direct Boric Acid application, has been applied to an ongoing fission reaction, if applied within a reactor or similar enclosed environmental construction, will eventually seal a breech in that environmental construction.</claim-text> <claim-text>4. The Proteus Boron Shut Down Process recited in elaimi, wherein the molten Boron Trioxide, either directly itself or having evolved from a direct Boric Acid application, has been applied to an ongoing fission reaction, if applied within a reactor or similar enclosed environmental construction, will fully isolate or enclose any exposed fuel component, leading to a suppression of neutron reactions.</claim-text> <claim-text>5. The Proteus Boron Shut Down Process recited in claim I, wherein the molten Boron Trioxide, either directly itself or having evolved from a direct Boric Acid application, has been applied to an ongoing fission reaction, if applied within a reactor or similar enclosed environmental construction, will fully iso fate or enclose any sloughed or broken off fuel elements, leading to a suppression of neutron reactions.</claim-text> <claim-text>6. The Proteus Boron Shut Down Process recited in elaimi, wherein the molten Boron Trioxide, either directly itself or having evolved from a direct Boric Acid application, has been applied to an ongoing fission reaction, if applied within a reactor or similar enclosed environmental construction, will eventually lead to a cool shut down or system equivalent, by the active suppression ofongoing neutron reactions.</claim-text> <claim-text>7. The Proteus Boron Shut Down Process recited in claim I, wherein the molten Boron Trioxide, either directly itself or having evolved from a direct Boric Acid application, has been applied to an ongoing fission reaction, if applied within a reactor or similar enclosed environmental construction, will by the convection currents within the molten Boron Trioxide flux', lead to an even dispersion of radiological contaminants, when the Flux' eventually cools to provide a vitrification (equivalent) environment.Authors: Gary T. Steadinan, Chas Ingham, Marc Naroshkhyn -Directors -Proteus Applied Technologies Ltd, Proteus Applied Technologies International Incorporated</claim-text>
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1121843.5A GB2497756A (en) | 2011-12-19 | 2011-12-19 | A process for the rapid shut-down of nuclear fission reactions |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1121843.5A GB2497756A (en) | 2011-12-19 | 2011-12-19 | A process for the rapid shut-down of nuclear fission reactions |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB201121843D0 GB201121843D0 (en) | 2012-02-01 |
| GB2497756A true GB2497756A (en) | 2013-06-26 |
Family
ID=45572666
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB1121843.5A Pending GB2497756A (en) | 2011-12-19 | 2011-12-19 | A process for the rapid shut-down of nuclear fission reactions |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB2497756A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2015079075A1 (en) * | 2013-11-26 | 2015-06-04 | Ingenieria Y Marketing, S.A. | Portable device for the boration of continuously flowing water |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57125885A (en) * | 1981-01-30 | 1982-08-05 | Hitachi Ltd | Device for injecting boric acid solution |
| JPH01196597A (en) * | 1988-02-01 | 1989-08-08 | Mitsubishi Atom Power Ind Inc | Emergency shutdown apparatus of nuclear reactor |
| JPH01295196A (en) * | 1988-05-23 | 1989-11-28 | Toshiba Corp | Boric acid water injection device |
| JPH02272394A (en) * | 1989-04-13 | 1990-11-07 | Toshiba Corp | Boric acid water charging device |
| JPH06174870A (en) * | 1992-12-10 | 1994-06-24 | Ishikawajima Harima Heavy Ind Co Ltd | Light-water cooled reactor |
| JP2007101332A (en) * | 2005-10-04 | 2007-04-19 | Toshiba Corp | Aqueous boric acid solution injector and aqueous boric acid solution injection method |
-
2011
- 2011-12-19 GB GB1121843.5A patent/GB2497756A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57125885A (en) * | 1981-01-30 | 1982-08-05 | Hitachi Ltd | Device for injecting boric acid solution |
| JPH01196597A (en) * | 1988-02-01 | 1989-08-08 | Mitsubishi Atom Power Ind Inc | Emergency shutdown apparatus of nuclear reactor |
| JPH01295196A (en) * | 1988-05-23 | 1989-11-28 | Toshiba Corp | Boric acid water injection device |
| JPH02272394A (en) * | 1989-04-13 | 1990-11-07 | Toshiba Corp | Boric acid water charging device |
| JPH06174870A (en) * | 1992-12-10 | 1994-06-24 | Ishikawajima Harima Heavy Ind Co Ltd | Light-water cooled reactor |
| JP2007101332A (en) * | 2005-10-04 | 2007-04-19 | Toshiba Corp | Aqueous boric acid solution injector and aqueous boric acid solution injection method |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2015079075A1 (en) * | 2013-11-26 | 2015-06-04 | Ingenieria Y Marketing, S.A. | Portable device for the boration of continuously flowing water |
| US10210957B2 (en) | 2013-11-26 | 2019-02-19 | Ingenieria Y Marketing, S.A. | Portable apparatus for the boration of continuously flowing water |
Also Published As
| Publication number | Publication date |
|---|---|
| GB201121843D0 (en) | 2012-02-01 |
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