JPS6155075B2 - - Google Patents

Info

Publication number
JPS6155075B2
JPS6155075B2 JP60008879A JP887985A JPS6155075B2 JP S6155075 B2 JPS6155075 B2 JP S6155075B2 JP 60008879 A JP60008879 A JP 60008879A JP 887985 A JP887985 A JP 887985A JP S6155075 B2 JPS6155075 B2 JP S6155075B2
Authority
JP
Japan
Prior art keywords
subcriticality
fuel
equation
neutron
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.)
Expired
Application number
JP60008879A
Other languages
English (en)
Japanese (ja)
Other versions
JPS61105492A (ja
Inventor
Kyoshi Ueda
Fumio Kurosawa
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.)
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
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 Toshiba Corp, Nippon Genshiryoku Jigyo KK filed Critical Toshiba Corp
Priority to JP60008879A priority Critical patent/JPS61105492A/ja
Publication of JPS61105492A publication Critical patent/JPS61105492A/ja
Publication of JPS6155075B2 publication Critical patent/JPS6155075B2/ja
Granted 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)
JP60008879A 1985-01-21 1985-01-21 未臨界度の測定方法 Granted JPS61105492A (ja)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60008879A JPS61105492A (ja) 1985-01-21 1985-01-21 未臨界度の測定方法

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60008879A JPS61105492A (ja) 1985-01-21 1985-01-21 未臨界度の測定方法

Publications (2)

Publication Number Publication Date
JPS61105492A JPS61105492A (ja) 1986-05-23
JPS6155075B2 true JPS6155075B2 (enrdf_load_stackoverflow) 1986-11-26

Family

ID=11704956

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60008879A Granted JPS61105492A (ja) 1985-01-21 1985-01-21 未臨界度の測定方法

Country Status (1)

Country Link
JP (1) JPS61105492A (enrdf_load_stackoverflow)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0442941Y2 (enrdf_load_stackoverflow) * 1990-11-08 1992-10-12
JP5330489B2 (ja) * 2011-12-01 2013-10-30 株式会社東芝 使用済み燃料の健全性評価方法および装置

Also Published As

Publication number Publication date
JPS61105492A (ja) 1986-05-23

Similar Documents

Publication Publication Date Title
KR910007146B1 (ko) 임계상태 접근을 결정하는 방법 및 장치
Hsue et al. Nondestructive assay methods for irradiated nuclear fuels
US20070076839A1 (en) Axial void fraction distribution measurement method and neutron multiplication factor evaluating method
Menlove Description and performance characteristics for the neutron coincidence collar for the verification of reactor fuel assemblies
Abdurrahman et al. Spent-fuel assay performance and Monte Carlo analysis of the Rensselaer slowing-down-time spectrometer
JP2542883B2 (ja) 照射燃料装荷未臨界体系の実効増倍率測定法
JPS6155075B2 (enrdf_load_stackoverflow)
JPH0659085A (ja) 使用済燃料集合体の未臨界度測定システム及び未臨界度測定方法
JP3026455B2 (ja) 照射燃料集合体の燃焼度測定方法
JPH0426718B2 (enrdf_load_stackoverflow)
JPS6045394B2 (ja) 未臨界度の測定方法
JPH01199195A (ja) 照射燃料装荷未臨界体系の実効増倍率測定法
Crow et al. Thermal neutron measurements of the Rhode Island Nuclear Science Center reactor after conversion to a compact low enriched uranium core
JP4664645B2 (ja) 照射燃料集合体の中性子放出率測定方法
Yokoyama et al. Neutron emission characteristics of spent boiling water reactor fuel
Leconte et al. Reactivity loss validation of high-burnup PWR fuels with pile-oscillation experiments in MINERVE
Lancaster et al. Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel—I: Methodology Overview
Menlove et al. The verification of reactor operating history using the fork detector
Gatchalian et al. Analysis of Loss of Water Inventory at the Philippine Research Reactor-1 Fuel Storage Facility.
Radulescu et al. Review of Experimental Data for Validating Computer Codes Used in Shielding Calculations for Spent Fuel Storage and Transportation Systems
Brady et al. Burnup credit issues in transportation and storage
Sakurai et al. Measurement and analysis of reactivity worth of 241Am sample in water-moderated low-enriched UO2 fuel lattices at TCA
Grouiller et al. Neutron Monitoring and the Inherent Source of Superphénix
JP2023031564A (ja) 使用済み混合酸化物燃料の臨界管理方法および使用済み混合酸化物燃料臨界安全評価装置
Winston et al. Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation