Abstract
To utilize the merit of supercritical water cooling, the Super FBR core concept, which is compatible with both the high breeding and the high enthalpy rise needs to be developed. One possible solution to meet such requirements may be to compose an axially heterogeneous core with MOX and blanket layers, with consideration of the large density change and specific heat of supercritical water at vicinity of the pseudocritical point. A new design concept of Super FBR has been proposed with “with multi-axial fuel shuffling”, which has flexibility in designing fuel shuffling schemes in the lower part and upper part of the core independently. Fully coupled neutronics and thermal-hydraulics core calculations were carried out to investigate impact of designing independent number of fuel batches and shuffling patterns in the upper and the lower parts of the core. Promising results were obtained, showing possibility of improving the core breeding performance with respect to the compound system doubling time (CSDT) by reducing the reactor doubling time (RDT) with designing of the independent fuel shuffling. Moreover, reduction in the ex-core factor (EF) was shown to be possible with such independent fuel shuffling. The combined effects of reductions in RDT and EF showed significant reduction in CSDT. It is the first design concept of Super FBR with coolant enthalpy rise, which covers from the liquid like state (below the pseudo-critical point) to the gas-like state (above the pseudo-critical point) of supercritical water. Further design investigations may be necessary to reduce CSDT and increase the average core outlet temperature.
| Original language | English |
|---|---|
| Pages (from-to) | 45-53 |
| Number of pages | 9 |
| Journal | Nuclear Engineering and Design |
| Volume | 324 |
| DOIs | |
| Publication status | Published - 2017 Dec 1 |
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Keywords
- Compound system doubling time (CSDT)
- Fast breeder reactor (FBR)
- Multi-axial fuel shuffling
- Supercritical pressure light water reactor (SCWR)
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering
Cite this
Flexible core design of Super FBR with multi-axial fuel shuffling. / Noda, Shogo; Someya, Takayuki; Yamaji, Akifumi.
In: Nuclear Engineering and Design, Vol. 324, 01.12.2017, p. 45-53.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Flexible core design of Super FBR with multi-axial fuel shuffling
AU - Noda, Shogo
AU - Someya, Takayuki
AU - Yamaji, Akifumi
PY - 2017/12/1
Y1 - 2017/12/1
N2 - To utilize the merit of supercritical water cooling, the Super FBR core concept, which is compatible with both the high breeding and the high enthalpy rise needs to be developed. One possible solution to meet such requirements may be to compose an axially heterogeneous core with MOX and blanket layers, with consideration of the large density change and specific heat of supercritical water at vicinity of the pseudocritical point. A new design concept of Super FBR has been proposed with “with multi-axial fuel shuffling”, which has flexibility in designing fuel shuffling schemes in the lower part and upper part of the core independently. Fully coupled neutronics and thermal-hydraulics core calculations were carried out to investigate impact of designing independent number of fuel batches and shuffling patterns in the upper and the lower parts of the core. Promising results were obtained, showing possibility of improving the core breeding performance with respect to the compound system doubling time (CSDT) by reducing the reactor doubling time (RDT) with designing of the independent fuel shuffling. Moreover, reduction in the ex-core factor (EF) was shown to be possible with such independent fuel shuffling. The combined effects of reductions in RDT and EF showed significant reduction in CSDT. It is the first design concept of Super FBR with coolant enthalpy rise, which covers from the liquid like state (below the pseudo-critical point) to the gas-like state (above the pseudo-critical point) of supercritical water. Further design investigations may be necessary to reduce CSDT and increase the average core outlet temperature.
AB - To utilize the merit of supercritical water cooling, the Super FBR core concept, which is compatible with both the high breeding and the high enthalpy rise needs to be developed. One possible solution to meet such requirements may be to compose an axially heterogeneous core with MOX and blanket layers, with consideration of the large density change and specific heat of supercritical water at vicinity of the pseudocritical point. A new design concept of Super FBR has been proposed with “with multi-axial fuel shuffling”, which has flexibility in designing fuel shuffling schemes in the lower part and upper part of the core independently. Fully coupled neutronics and thermal-hydraulics core calculations were carried out to investigate impact of designing independent number of fuel batches and shuffling patterns in the upper and the lower parts of the core. Promising results were obtained, showing possibility of improving the core breeding performance with respect to the compound system doubling time (CSDT) by reducing the reactor doubling time (RDT) with designing of the independent fuel shuffling. Moreover, reduction in the ex-core factor (EF) was shown to be possible with such independent fuel shuffling. The combined effects of reductions in RDT and EF showed significant reduction in CSDT. It is the first design concept of Super FBR with coolant enthalpy rise, which covers from the liquid like state (below the pseudo-critical point) to the gas-like state (above the pseudo-critical point) of supercritical water. Further design investigations may be necessary to reduce CSDT and increase the average core outlet temperature.
KW - Compound system doubling time (CSDT)
KW - Fast breeder reactor (FBR)
KW - Multi-axial fuel shuffling
KW - Supercritical pressure light water reactor (SCWR)
UR - http://www.scopus.com/inward/record.url?scp=85028760925&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85028760925&partnerID=8YFLogxK
U2 - 10.1016/j.nucengdes.2017.08.025
DO - 10.1016/j.nucengdes.2017.08.025
M3 - Article
AN - SCOPUS:85028760925
VL - 324
SP - 45
EP - 53
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
SN - 0029-5493
ER -