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2021:05 Cladding tube rupture under LOCA: Data and models for rupture opening size
coolant in case of an accident. This risk depends on complex conditions were one is the possibility and size of a rupture of the fuel rod cladding tube. The work presented in this report is part of a larger ... continuation of the development of cladding rupture criteria and fuel fragmentation models in previous projects. The present report analyses test results and deduces a model that can be used to predict fuel cladding...
Content type: Publications -
2021:04 Calibration of models for cladding tube high-temperature creep and rupture in the FRAPTRAN-QT-1.5 program
stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally ... to predict and very hard to study since it occurs suddenly and often unexpectedly. In order to study the crack initiation and growth, the crack is traditionally experimentally provoked and it is not known...
Content type: Publications -
2021:03 Updated radiological risk assessment for the “Radon” type surface disposal facility in Chisinau, Moldova
SSM perspective Background Bilateral cooperation between Sweden and the Republic of Moldova in nuclear and radiological safety and security has been ongoing since 2010, focusing on activities aimed at ... National Agency for Regulation of Nuclear and Radiological Activities in Moldova (NARNRA) as well as infrastructure development in radioactive waste management, handling and treatment at the Radioactive Waste...
Content type: Publications -
2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling
stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally ... to predict and very hard to study since it occurs suddenly and often unexpectedly. In order to study the crack initiation and growth, the crack is traditionally experimentally provoked and it is not known...
Content type: Publications -
2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint
for crack assessment. However, predictions of the crack opening displacement will be overestimated and hence the calculated leakage rate. The present study aims to investigate what impacts the assumption ... leak-before-break assessments and leakage rate calculations. Results The study conclude that crack opening displacements were influenced by restraint length, relative crack length, degree of restraint and material constitutive...
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2020:15e Protective Actions in Nuclear or Radiological Emergencies - Planning Basis for Events in Emergency Preparedness Category IV
In this report, the Swedish Radiation Safety Authority (SSM) presents planning basis for protective actions in the event ... of nuclear or radiological emergencies in connection with activities and acts in emergency preparedness category IV. Activities and acts encompass events in activities with ionizing radiation that are...
Content type: Publications -
2020:12 Assessment of the QT-COOL coolant channel module against the PBF RIA 1-2 experiment
possibility for SSM to do own analysis of fuel rods in reactivity initiated accidents. The development and administration of the program is done by Quantum Technologies AB on assignment from SSM. SSM’s development ... thermohydraulic model in SCANAIR was proposed and implemented in an SSM-specifc version of SCANAIR V_7_6. The present work is the 2020 contribution to SCANAIR development and contains a validation against tests...
Content type: Publications -
2020:13 Core data Research at Uppsala University
nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data ... nuclear safeguards, medicine, final repository etc. This project measured different nuclear reactions and developed theoretical nuclear data models. The experiments were focused on fission reactions. The experiments...
Content type: Publications -
2020:11 Competency based assessments of Nuclear Power Plant controlroom operators
Experiences of development and first operational methodological and technical demonstrator application...
Content type: Publications -
2020:07 Fibre Clogging in Nuclear Power Plants
SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to out foreign material suspended in the cooling water so this material ... increased pressure drop over strainers, potentially causing cavitation in the emergency cooling pumps and an excessively reduced l. An increase in the surface size of the strainers has the side effect of more...
Content type: Publications