Role of Nuclear Energy and University Research Yoshiaki Oka Professor, Waseda University Shinjuku‐ku, Tokyo, Japan Emeritus professor, University of Tokyo Special panel session celebrating the 75 th anniversary of the discovery of fission , November 13, 2013, American Nuclear Society, Winter Meeting. Washington DC, USA 1
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Role of Nuclear Energy and University Research of Nuclear Energy and University Research Yoshiaki Oka Professor, WasedaUniversity Shinjuku‐ku, Tokyo, Japan Emeritus professor, University
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Role of Nuclear Energy and University Research
Yoshiaki OkaProfessor, Waseda UniversityShinjuku‐ku, Tokyo, Japan
Emeritus professor, University of Tokyo
Special panel session celebrating the 75th anniversary of the discovery of fission , November 13, 2013, American Nuclear Society, Winter Meeting. Washington DC, USA
1
Outline
• Energy sources, Global warming, Nuclear energy
• Role of University Research• Super LWR and Super FR studies, • High breeding by light water cooling, • R&D of Thermal hydraulics and materials• New textbooks of nuclear engineering
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Energy sources
3
Fossil fuels are major primary energy source since industrial revolution for 250 years
Transients Accidents ATWS without alternative action ATWS with alternative action (ADS)
1 2 3 4 9 1 2 3 5 6 1 2 3 4 6 7 9
Criterion for transient
Criterion for accident and ATWS
Event number
Incre
ase o
f te
mpera
ture
fro
m initia
l va
lue [
℃]
100
120
140
160
180
200
8 3 7 6 9
Criterion for powerrising rate of 0.1-1%
Criterion for power rising rate of 1-10%
Criterion for powerrising rate of ovre 10%
Transient number
Peak
pow
er
[%]
25
26
27
28
29
30
31
2 3 4 8 9
Transients Accidents ATWS without alternative action ATWS with alternative action (ADS)
3 4 2 3 4 7 8 9
Criterion for transient
Criterion for accident and ATWS
Event number
Peak
pre
ssure
[M
Pa]
Transients Accidents1. Partial loss of reactor coolant flow2. Loss of offsite power3. Loss of turbine load4. Isolation of main steam line5. Pressure control system failure6. Loss of feedwater heating 7. Inadvertent startup of AFS8. Reactor coolant flow control system failure9. Uncontrolled CR withdrawal at normal operation10. Uncontrolled CR withdrawal at startup
1. Total loss of reactor coolant flow 2. Reactor coolant pump seizure3. CR ejection at full power 4. CR ejection at hot standby5. Large LOCA 6. Small LOCA
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Super FRa fast reactor concept
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Advantages of Super Fast Reactor Same plant system as Super LWRHigh power density of Super FR is an advantage in capital cost over Super LWR and LWR Capital cost; Super FR< Super LWR< LWR
Low reactor coolant flow rate (due to high enthalpy rise) High head pumps Suitable for tight fuel lattice core of Super FR No pumping power increase and instability problems of high conversion LWR
Coolant flow schemes of Super FR
Fuel assemblies and core of Super FR
seed fuel assembly
blanket assembly Loading pattern of one path core
Super FR (one pass core) characteristics
Power MWt/MWe 2337/1006Coolant pressure (MPa) 25.0Inlet/outlet temperature (oC) 280/501Active/overall power density (kW/L) 206/149Number of seed assembly 78Number of blanket assembly 37Active core height (m) 2.4Eq. active core diameter (m) 2.47Pu enrichment in seed assembly (wt%) 32(bottom)/25(top)Pu enrichment in bottom blanket (wt%) 10(bottom)Cycle length (EFPD)/fuel batch 200/3Average/max discharge burn-up (GWd/t) 53.8/72.7
High breeding by light water cooling
Tightly packed-rods fuel assembly
breeding core
Characteristics of high breeding core and comparison with RMWR (reduced moderation BWR)
Scope of studies and Computer codes1.Fuel and core
Single channel thermal hydraulics (SPROD), 3D coupled coreneutronic/thermal-hydraulic (SRAC-SPROD), Coupled sub-channel analysis, Statistical thermal design method, Fuel rodbehavior (FEMAXI-6), Data base of heat transfer coefficientsof supercritical water
2. Plant system; Plant heat balance and thermal efficiency3. Plant control4. Safety; Transient and accident analysis at supercritical-and
subcritical pressure, ATWS analysis, LOCA analysis (SCRELA)5. Start-up (sliding-pressure and constant-pressure)6. Stability (TH and core stabilities at supercritical and
43Super Fast Reactor R&D1st Phase (2005‐ 2010), 2nd phase (2010‐2014)
1st phase: University of Tokyo, JAEA, Kyushu Univ. and TEPCO2nd phase: Waseda University, Univ. of Tokyo, JAEA, Kyushu Univ. Tohoku univ. TEPCO systemsentrusted by MEXT
Supercritical water at JAEA1. Single rod/rod bundle experiment2. Single tube experiment at high temperature 45
Materials R&D• Developed 15Cr‐20Ni SS cladding material based on cladding material for LMFBR
• Developed thermal insulating material, Yttria‐stabilized zirconia (YSZ)
• Measurement of Corrosion and elusion characteristics of cladding materials
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Mass transfer experimentsElusion and deposition characteristics from 20C to 550C and to 20C
Diagram of mass transfer experiment loop
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Control system
Super LWR design study started in 1989.
Results of the design study (until 2009) are summarized.
Also a textbook of reactor design and anlysis: Core & fuel design, plant control, start‐up, plant heat balance, stability, safety design and analysis of Super LWR and Super FR as well as the comutational methods
Publidhed in July 2010 from Springer
2nd book “ supercritical pressure light water cooled reactors” is under preparation. 48
Contents: PSA in design and maintenance of ABWR, Passive ECCS of APWR, Severe accident mitigation features of APR1400, EPR core catcher, Severe accident research in China, Full MOX core design of ABWR, CFD applications, Digital I&C system, 3D-CAD application to construction, Progress in seisimic design
Available from Springer, 295 pages
Based on the lectures of International summer school of NPP and young generation work shop“; Bridgeing fundamental research and practical applications” in 2009 in Tokai-mura Japan