GB201121843D0 - Proteus boron - Google Patents

Proteus boron

Info

Publication number
GB201121843D0
GB201121843D0 GBGB1121843.5A GB201121843A GB201121843D0 GB 201121843 D0 GB201121843 D0 GB 201121843D0 GB 201121843 A GB201121843 A GB 201121843A GB 201121843 D0 GB201121843 D0 GB 201121843D0
Authority
GB
United Kingdom
Prior art keywords
reaction
chamber
boron trioxide
vessel
nuclear fission
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
Application number
GBGB1121843.5A
Other versions
GB2497756A (en
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
INGHAM CHARLES D
PROTEUS APPLIED TECHNOLOGY Ltd
Original Assignee
INGHAM CHARLES D
PROTEUS APPLIED TECHNOLOGY Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by INGHAM CHARLES D, PROTEUS APPLIED TECHNOLOGY Ltd filed Critical INGHAM CHARLES D
Priority to GB1121843.5A priority Critical patent/GB2497756A/en
Publication of GB201121843D0 publication Critical patent/GB201121843D0/en
Publication of GB2497756A publication Critical patent/GB2497756A/en
Pending legal-status Critical Current

Links

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.
GB1121843.5A 2011-12-19 2011-12-19 A process for the rapid shut-down of nuclear fission reactions Pending GB2497756A (en)

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 true GB201121843D0 (en) 2012-02-01
GB2497756A 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)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
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

Family Cites Families (6)

* Cited by examiner, † Cited by third party
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

Also Published As

Publication number Publication date
GB2497756A (en) 2013-06-26

Similar Documents

Publication Publication Date Title
MY164097A (en) Integral molten salt reactor
US10445160B2 (en) Remote monitoring of critical reactor parameters
WO2013041085A3 (en) Dual fluid reactor
RU2014117676A (en) NUCLEAR REACTORS AND WAYS AND DEVICES RELATED TO THEM
KR102225854B1 (en) Method of cooling nuclear reactor and nuclear reactor including polyhedral boron hydride or Carborane anions
GB201121843D0 (en) Proteus boron
MX339578B (en) Methods for protection nuclear reactors from thermal hydraulic/neutronic core instability.
GB201121841D0 (en) Proteus fast shut down
MX2015008475A (en) Containment vent system with passive mode for boiling water reactors (bwrs) and method thereof.
ES2870600T3 (en) Nuclear fuel storage pool that includes an aqueous solution of polyhedral boron hydride anions or carborane anions and methods of using the same
Rojas Sodium-Cooled Fast Reactors as a Generation IV Nuclear Reactor
Makhijani Post-Tsunami Situation at the Fukushima Daiichi Nuclear Power Plant in Japan: Facts, Analysis, and Some Potential Outcomes
Hayes Metallic Fuels for Fast Reactors
CN102842345A (en) Application of technetium-99 as burnable poison element
RU2512472C1 (en) Guide channel for fuel assembly of nuclear reactor with burnable absorber
Steinhauser et al. Dihydrogen gas emission of a 250 kWth research reactor
JP2011141198A (en) Radiation shielding liquid and radiation shield
Shadrin et al. Reprocessing of fast reactors mixed U-Pu used nuclear fuel: Studies and industrial test
GB201121839D0 (en) Proteus delivery system
Reno et al. Decommissioning safety infrastructure of nuclear facilities in Indonesia
Felten Generation III reactors safety requirements and the design solutions
Shin Safety review of severe accident senario for wet spent fuel storage facility
JOP20180106A1 (en) Fuel composition for water-cooled reactors of NPPs on thermal neutrons
Bambang The identification of safety provision for establishment of BAPETEN chairman regulation related to the construction of solution reaktor
Cheng et al. Nuclear power accidents and its development prospects