UST939002I4 - Epithermal nuclear reactor - Google Patents

Epithermal nuclear reactor Download PDF

Info

Publication number
UST939002I4
UST939002I4 US35237273A UST939002I4 US T939002 I4 UST939002 I4 US T939002I4 US 35237273 A US35237273 A US 35237273A US T939002 I4 UST939002 I4 US T939002I4
Authority
US
United States
Prior art keywords
reactor
nuclear
core
epithermal
nuclear reactor
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
Other languages
English (en)
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 filed Critical
Priority to US35237273 priority Critical patent/UST939002I4/en
Priority to JP4182774A priority patent/JPS5338397B2/ja
Application granted granted Critical
Publication of UST939002I4 publication Critical patent/UST939002I4/en
Pending legal-status Critical Current

Links

Images

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • 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

Definitions

  • a supercritical nuclear reactor having a core which includes fuel elements containing a mixture of beryllium oxide and enriched uranium.
  • the combination of beryllium oxide in the fuel and the reactor coolant, comprising light Water, provides nuclear moderation such that the reactor operates Within the cpitherlnal energy spectrum.
  • the reactor coolant achieves operating conditions by making three or more passes through the nuclear core.
  • Reactor control is accomplished by boron carbide control rods located Within the nuclear core.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
US35237273 1973-04-18 1973-04-18 Epithermal nuclear reactor Pending UST939002I4 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
US35237273 UST939002I4 (en) 1973-04-18 1973-04-18 Epithermal nuclear reactor
JP4182774A JPS5338397B2 (enrdf_load_stackoverflow) 1973-04-18 1974-04-16

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US35237273 UST939002I4 (en) 1973-04-18 1973-04-18 Epithermal nuclear reactor

Publications (1)

Publication Number Publication Date
UST939002I4 true UST939002I4 (en) 1975-10-07

Family

ID=23384864

Family Applications (1)

Application Number Title Priority Date Filing Date
US35237273 Pending UST939002I4 (en) 1973-04-18 1973-04-18 Epithermal nuclear reactor

Country Status (2)

Country Link
US (1) UST939002I4 (enrdf_load_stackoverflow)
JP (1) JPS5338397B2 (enrdf_load_stackoverflow)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4233116A (en) 1975-06-10 1980-11-11 Westinghouse Electric Corp. Nuclear reactor coolant transport system

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5650088Y2 (enrdf_load_stackoverflow) * 1978-02-10 1981-11-24
JPH079473B2 (ja) * 1989-02-07 1995-02-01 動力炉・核燃料開発事業団 燃料集合体
KR20220077147A (ko) * 2019-10-15 2022-06-08 뉴스케일 파워, 엘엘씨 원자로로부터의 열 제거와 같은 열 제거를 위한 히트 파이프 네트워크와, 관련 시스템 및 방법

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4233116A (en) 1975-06-10 1980-11-11 Westinghouse Electric Corp. Nuclear reactor coolant transport system

Also Published As

Publication number Publication date
JPS5338397B2 (enrdf_load_stackoverflow) 1978-10-14
JPS508991A (enrdf_load_stackoverflow) 1975-01-29

Similar Documents

Publication Publication Date Title
UST921019I4 (en) Core for a nuclear reactor
UST939002I4 (en) Epithermal nuclear reactor
Seaborg et al. Fast breeder reactors
Golay et al. Advanced light-water reactors
US2796398A (en) Means for sustaining a nuclear fission chain reaction
UST937001I4 (en) Comtois etal thermal nuclear reactor
US3253997A (en) Nuclear reactor and cooling and moderating arrangement therefor
US3523869A (en) Booster-source rods in heavy water moderated reactor
GB1029712A (en) Improvements in or relating to nuclear reactors
UST909020I4 (en) Combined solid and liquid system for controlling nuclear reactors
Hendrie Nuclear power plants: Structure and function
Lewis Nuclear reactions
AT212462B (de) Thermischer Kernreaktor mit organischem Moderator
Burtak et al. Use of Weapons-Grade Plutonium in Existing PWRs—Supported by German MOX Recycling Experience
Runnalls Plutonium Utilization in Canada
Aschner et al. Feasibility of Nuclear Reactors for Sea Water Distillation in Israel
Herron et al. An Evaluation of Heavy Water Reactors for Power
Buono et al. Improvements to trino-E. Fermi-NPP to up-date safety to modern standards and to increase life expectancy
GB1098623A (en) Improvements in or relating to liquid moderated nuclear reactors
Sofer Conceptual Design and Economic Evaluation of a Steam-cooled Fast Breeder Reactor
OHTA The comparative study of the sodium loss reactivity effect of large Pu-U and Pu-Th fast reactors
Sawai et al. Design of Pu Self-Sustaining Reactor with D2O Moderator and Boiling H2O Coolant
Dent et al. Britain's steam-generating heavy-water reactor
DE1027808B (de) Siedewasserreaktor
Ermakov et al. Nuclear power plant