2014
DOI: 10.1016/j.pnucene.2014.01.011
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Overview and progress in the European project: “Supercritical Water Reactor – Fuel Qualification Test”

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Cited by 21 publications
(3 citation statements)
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“…A fuel qualification test based on the three-pass core concept is planned. A fuel bundle is being to be irradiated at supercritical pressure conditions inside the LVR-15 research reactor in Rez, Czech Republic [22]. In support of the fuel qualification testing, the out-of-pile test in an electrically heated, but otherwise identical, fuel assembly is carried out at Shanghai Jiaotong University (SJTU).…”
Section: Introductionmentioning
confidence: 99%
“…A fuel qualification test based on the three-pass core concept is planned. A fuel bundle is being to be irradiated at supercritical pressure conditions inside the LVR-15 research reactor in Rez, Czech Republic [22]. In support of the fuel qualification testing, the out-of-pile test in an electrically heated, but otherwise identical, fuel assembly is carried out at Shanghai Jiaotong University (SJTU).…”
Section: Introductionmentioning
confidence: 99%
“…Within a light water reactor (LRW) the primary coolant circuit typically operates at temperatures of 315 °C with pressures around 10 MPa, whereas in future designs such as the Supercritical Water Reactor (SCWR), as part of GEN IV reactors, considers approximate pressures and temperatures of 25 MPa and 370 °C. 25,26 Within the centre of LWR UO 2 fuels, HP/HT conditions can be more realised as the centreline fuel pellet temperature is held typically below 1400 °C27 and it has been estimated the internal pressures generated during He bubble…”
Section: Introductionmentioning
confidence: 99%
“…Within a light water reactor (LRW) the primary coolant circuit typically operates at temperatures of 315 °C with pressures around 10 MPa, whereas in future designs such as the Supercritical Water Reactor (SCWR), as part of GEN IV reactors, considers approximate pressures and temperatures of 25 MPa and 370 °C. 25,26 Within the centre of LWR UO 2 fuels, HP/HT conditions can be more realised as the centreline fuel pellet temperature is held typically below 1400 °C 27 and it has been estimated the internal pressures generated during He bubble formation can reach GPa level. 28 Within spent nuclear fuel (SNF) near-surface geological repositories, such as the planned Swedish Forsmark SNF repository, maximum pressures and temperatures of a few MPa and around 100 °C of these near surface facilities are predicted.…”
Section: Introductionmentioning
confidence: 99%