Nuclear Data Needs from Core Design
炉心設計側からの核データに対する要求

2. Advanced Reactors
2. 革新炉の核データニーズ
T. Yoshida
Musashi Institute of Technology

GFR:Gas-Cooled Fast reactor• features a fast-neutron-spectrum,
helium-cooled reactor and closed fuel cycle

VHTR:Very High Temperature Reactor• a graphite-moderated, helium-cooled
reactor with a once-through uranium fuel cycle

SCWR:Supercritical-Water Cooled Reactor•a high-temperature, high-pressure water-cooled
reactor that operates above the thermodynamic
critical point of water

SFR:Sodium Cooled Fast Reactor•features a fast-spectrum, sodium-cooled reactor
and closed fuel cycle for efficient management ofactinides and conversion of fertile uranium
LFR: Lead Cooled Fast Reactor•features a fast-spectrum lead of lead/bismuth
eutectic liquid metal-cooled reactor and a closed
fuel cycle for efficient conversion of fertile uranium
and management of actinides
MSR: Molten Salt Reactor•produces fission power in a circulating molten salt
fuel mixture with an epithermal-spectrum reactor
and a full actinide recycle fuel cycle

International Workshop on Nuclear Data
Needs for Generation IV Nuclear Energy
SystemsHotel Hilton Antwerp, Belgium April 5-7, 2005

Nuclear Data Needs for Generation IV Systems
Future of Nuclear Energy and the Role of Nuclear Data

P.Finck, ANL

Nuclear Data Needs for Generation IV Nuclear Energy
SystemsT.A.Taiwo, H.S.Khalil, ANL

Nuclear Data Needs for the Assessment of Gen. VI Systems

G.Rimpault, Cadarache

Nuclear Data Needs for Generation IV- Lesson fromBenchmarks

S.C. van der Marck et al., Petten

Core Design Issues of the Super Critical Water Fast Reactor

M.Mori, et al., karlsruhe & V. Sinista, IPPE Obninsk

Comparative Study on Differential Phonon Frequency
Spectra of Graphite

Young-Sik Cho, et al., KAERI

Innovative Fuel Types for Minor Actinide Transumutation

D.Haas, A.Fernandez, J.Somers, ITE, Karlsruhe

The Importance of Nuclear Data in Modeling and Designing
Generation IV Fast Reactor

K.D.Weaver, Idaho

The GIF and Mexico “Everything Begins with a Wish”

C.A.Sanches, ININ

Benchmarks, Sensitivity Calculation, Uncertainty
Sensitivity of Advanced Reactor and Fuel Cycle
Performance Parameters to Nuclear Data Uncertainties

G.Aliberti et al., ANL, NEA Data Bank, Cadarache~~ExperimentsRecent Measurements of Neutron capture Cross Section
For Minor Actinides by a JNC and Kyoto University Group

H.Harada et al., JNC (now JAEA), Kyoto University~Evaluated Data Libraries

System Studied
GFR: 2400 Mwe - He cooled; SiC - (U-TRU)C fuelZr3Si2 reflector; enrichment :17%, MA:5%
irradiation cycle:415 d

VHTR: TRISO fuel; enrichment:14%; burnup: 90 GW d/Kg
SFR: (Burner: CR=0.25) 840 MWt - Na cooled;
U-TRU-Zr metallic alloy; SS reflector;
enrichment: 56%, MA:10%; irradiation cycle:415 d

LFR: 900 MWth - Pb cooled; UTRU-Zr metallic
alloy;
Pb reflector; enrichment:21%, MA:2%,irradiation cycle:310 d
In addition:EFR, Extennded BU PWR(8.5% enrichment)Table Fast Neutron System - Total Uncertainty (%)

Table GFR. Uncertainties (%) PEC - Breakdown by Isotope

Table LFR. Uncertainties (%) PEC - Breakdown by Isotope

Fig. Pb-206 Inelastic Scattering Cross Section

Fig. Pb-208 Inelastic Scattering Cross Section

Table LFR. Uncertainties (%) PEC - Breakdown by Isotope

Their Conclusions
Data uncertainty are significant only for a fewparameters
Keff for all systems
Burup reactivity swing & isotopic density variations
Void coefficient in FRs

Despite a significant MA recycling, MA data donot
play a major role with some exceptions
Am-243 capture in the fast and thermal range
Am-242m fission in the fast rang

As for major actinides, besides U-238, Pu isotope
data uncertainties are very significant

Their Conclusions (cont’d)
As for structural/coolant materials, the mostsignificant data are:
Fe inelastic in Fe, Pb and Si. Na elastic

Better and more complete covariance matrices areneeded.
They do not need to be perfect, but reliable, andcomplete enough to make a relevant point clear.