JPS5495895A - Calculation method of neutron exposure against interior structure of fast reactor - Google Patents

Calculation method of neutron exposure against interior structure of fast reactor

Info

Publication number
JPS5495895A
JPS5495895A JP116178A JP116178A JPS5495895A JP S5495895 A JPS5495895 A JP S5495895A JP 116178 A JP116178 A JP 116178A JP 116178 A JP116178 A JP 116178A JP S5495895 A JPS5495895 A JP S5495895A
Authority
JP
Japan
Prior art keywords
neutron
neutron exposure
core
calculation method
exposure
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
JP116178A
Other languages
Japanese (ja)
Inventor
Hidesuke Matsushima
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP116178A priority Critical patent/JPS5495895A/en
Publication of JPS5495895A publication Critical patent/JPS5495895A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE: To obtain accurate neutron exposure in any position of interior core by combining the measurements of indcued radioactivity of neutron exposure calculation assembly provided within the core with calculated value obtained by calculation program.
CONSTITUTION: Neutron flux ϕ at the point to solve the differential equation of formula 1 is obtained, obtaining neutron exposure by time imtegration. Neutron flux distribution and neutron exposure of pellet arranged in one axial direction are detected. Neutron exposure of any position of the inside of core may be obtained by combining the calculated value with measurements. Regarding to calculated program, the transportation calculation program is preferable to the diffusion calculation program due to solving to the outside of the core.
COPYRIGHT: (C)1979,JPO&Japio
JP116178A 1978-01-11 1978-01-11 Calculation method of neutron exposure against interior structure of fast reactor Pending JPS5495895A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP116178A JPS5495895A (en) 1978-01-11 1978-01-11 Calculation method of neutron exposure against interior structure of fast reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP116178A JPS5495895A (en) 1978-01-11 1978-01-11 Calculation method of neutron exposure against interior structure of fast reactor

Publications (1)

Publication Number Publication Date
JPS5495895A true JPS5495895A (en) 1979-07-28

Family

ID=11493703

Family Applications (1)

Application Number Title Priority Date Filing Date
JP116178A Pending JPS5495895A (en) 1978-01-11 1978-01-11 Calculation method of neutron exposure against interior structure of fast reactor

Country Status (1)

Country Link
JP (1) JPS5495895A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006118904A (en) * 2004-10-20 2006-05-11 Hitachi Ltd Arrangement for measuring radiation damage degree

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006118904A (en) * 2004-10-20 2006-05-11 Hitachi Ltd Arrangement for measuring radiation damage degree
JP4587769B2 (en) * 2004-10-20 2010-11-24 日立Geニュークリア・エナジー株式会社 Radiation damage measuring device

Similar Documents

Publication Publication Date Title
JPS5495895A (en) Calculation method of neutron exposure against interior structure of fast reactor
JPS5267686A (en) Device for measuring spacial distribution of neutrons
JPS5356495A (en) Neutron measurement unit within reactor
JPS5440996A (en) Power distribution deducing method
JPS52152278A (en) Environmental radiant ray measuring method of surrounding site of atomic power plant etc.
JPS53107594A (en) Rector neutron flux detector
JPS53115494A (en) Fuel particle distribution measurement of nuclear fuel compact
JPS5352894A (en) Degree of burn-up measuring method in fuel assembly
JPS5219894A (en) Neutron detector
GB938120A (en) Nuclear reactor, the core of which contains a charge of fuel elements consisting of shaped bodies, such as balls
JPS533262A (en) Radiation thickness meter
JPS5259291A (en) Under parts structure of core in atomic pile
JPS52143398A (en) Core abnormal detecting device
JPS53109671A (en) Measuring method of density of fuel pellets for nuclear reactors
JPS53148400A (en) Radiant ray detector of semiconductor
JPS53120090A (en) Nuclear reactor
JPS542179A (en) Low concentration radioactive gas measuring apparatus provided with enrichment rate corrector
JPS53117195A (en) Incore neutron detector fuel assembly
JPS5352893A (en) Measuring method and device for reactivity of reactor fuel assembly
JPS53117193A (en) Non-destructive measurement of plutonium 239 and uranium 235 of irradiation fuel assembly
JPS5421523A (en) Axial displacement detector for transformer winding
DE2963198D1 (en) Nuclear reactor plant with an arrangement of neutron flux measuring instrumentation
JPS5293896A (en) Output of reactor measuring method and its device
JPS5364193A (en) Nuclear reactor output distribution correction method
JPS52125266A (en) Cathode constant length welder unit in cathode ray tube