[go: up one dir, main page]

Sundari et al., 2025 - Google Patents

Design and Operational Procedure of Sipping Test for Assessing Leakage of MTR Spent Nuclear Fuel from GA Siwabessy Research Reactor in a Wet Storage Facility

Sundari et al., 2025

Document ID
12500380548175282780
Author
Sundari T
Rachmadetin J
Suryantoro
Purwantara
Purwanto Y
Aji D
Parjono
Sudjadi U
Publication year
Publication venue
Nuclear Technology

External Links

Snippet

Assessing spent nuclear fuel (SNF) integrity is essential for ensuring radiation safety throughout its storage duration. One of the widely used methods is the sipping test, a nondestructive technique for detecting leaks in SNF by analyzing the release of radioactive …
Continue reading at www.tandfonline.com (other versions)

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/04—Detecting burst slugs
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008—Containers for fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2002/00—PROBLEM
    • G21Y2002/104—Inadequate performance, deformation, cracks, rupture
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2002/00—PROBLEM
    • G21Y2002/202—Slowness of a process or function
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
    • G21Y2004/00—SOLUTION
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F7/00—Shielded cells or rooms
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T7/00—Details of radiation-measuring instruments
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation

Similar Documents

Publication Publication Date Title
Hanson et al. Gap analysis to support extended storage of used nuclear fuel, Rev. 0
CN107507655A (en) The recognition methods of thermometric graphite nodule and device in a kind of HTGR
Saegusa et al. Monitoring of helium gas leakage from canister storing spent nuclear fuel: Radiological consequences and management
Fensin et al. A Monte Carlo linked depletion spent fuel library for assessing varied nondestructive assay techniques for nuclear safeguards
Sagara et al. Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy–low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris: Fukushima NPP Accident Related
Sundari et al. Design and Operational Procedure of Sipping Test for Assessing Leakage of MTR Spent Nuclear Fuel from GA Siwabessy Research Reactor in a Wet Storage Facility
Kaplan-Trahan et al. Spent Fuel Measurements
Park et al. Estimating spent fuel burnup with Neutron measurements: A Practical Rule of Thumb Equation
Jensen et al. Restart of the transient reactor test (TREAT) facility neutron radiography program
Kim et al. Application of safeguards-by-design for the pyroprocessing facilities in the rok
Fensin et al. A Monte Carlo based spent fuel analysis safeguards strategy assessment
Rodrigues et al. Designing a system to detect leaking in fuel elements in Brazilian Triga research reactor
Jafari et al. A sipping test simulator for identifying defective fuels in MTR type nuclear research reactor
Furuta et al. Estimation of photon energy and direction distributions at Japanese nuclear power plants based on literature survey for J-EPISODE study
Patenaude et al. Oh, my darling clementine: A detailed history and data repository of the los alamos plutonium fast reactor
Phlippen et al. Numeric Determination and Validation of Neutron-Induced Radioactive Nuclide Inventories for Decommissioning and Dismantling of Light Water Reactors
Lehmann et al. The investigation of highly activated samples by neutron radiography at the spallation source SINQ
Mishra et al. Post Irradiation Examination of Fuel
Wang et al. The Design and Development of the Process Radiation Monitoring System of the High Temperature Gas-Cooled Reactor (HTGR) in China
Tayfur A Probabilistic Risk Assessment Study of a Pebble-bed High Temperature Gas Cooled Reactor Onsite Spent Fuel Storage System
Imholte et al. An approach for spent nuclear fuel containment integrity verification using gas tagging
Chichester et al. Capabilities of the INL ZPPR to support active interrogation research with SNM
Trtik et al. Nuclear materials
Cobb et al. Preliminary concepts: safeguards for spent light-water reactor fuels
Garrett et al. T Sobolev, DC Springfels Pacific Northwest National Laboratory