JAEA-Conf 2011-002 - 日本原子力研究開発機構

More documents

Recommendations

Info

JAEA-Conf 2011-002 Though words too many, however, what I have often heard is “Nuclear data are an important database for research and developments of nuclear applications. Target materials and kinds of nuclear data are different application by application. The new nuclear data are needed to be produced. Is it necessary to be done by Japan?” It is necessary for proper usage of nuclear data to know about the origin and background. In the case of nuclear data being produced in abroad, it has some difficulty to see it. And I also hear “Why do not consider the world-unified nuclear data file?” Since nuclear data are a kind of physical quantities, it must converge into certain values. However, it needs much more time to be fixed. Before it is achieved, it is necessary to produce country by country, or area by area, so that they can choose their own purpose of developing nuclear data and keep competition opportunity to upgrade nuclear data quality
JAEA-Conf 2011-002 Minoru GOTO 1 , Satoshi SHIMAKAWA 1 and Takashi YASUMOTO 2 1. Japan Atomic Energy Agency, 4002, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan 2. Kyushu University, 744, Motooka, Nishi-ku, Fukuoka-city 819-0395, Japan e-mail: goto.minoru@jaea.go.jp In the past, benchmark calculations of criticality approach for the HTTR, which is a Japanese HTGR, were performed by research institutes in several countries, and almost all of the calculations overestimated the excess reactivity. In Japan, the benchmark calculations performed by JAEA also resulted in overestimation. JAEA improved the calculations by revising the geometric model and replacing the nuclear data library with JENDL-3.3, which was the latest JENDL at that time. However, the overestimation remained and this problem has not been resolved until today. We performed calculations of the HTTR criticality approach with several nuclear data libraries, and found that slight difference in the capture cross section of carbon at thermal energy among the libraries causes significant difference in the keff values. The cross section value of carbon was not concerned in reactor neutronics calculation because of its small value of the order of 10 -3 burn, and consequently the cross section value was not revised for a long time even in the major nuclear data libraries: JENDL, ENDF and JEFF. We thought that the cross section value should be revised based on the latest measurement data in order to improve the accuracy of the neutronics calculations of the HTTR. In May 2010, the latest JENDL: JENDL-4.0 was released by JAEA, and the capture cross section of carbon was revised. Consequently, JENDL-4.0 yielded 0.4-0.9%k smaller keff values than JENDL-3.3 in the calculation of the HTTR critical approach, and then the problem of the overestimation of the excess reactivity in the HTTR benchmark calculation was resolved. 1. Introduction In the past, the neutronics calculations for the HTTR critical approach were performed with the three major nuclear data libraries, which are JENDL-3.3 (Japan), ENDF/B-VI.8 (U.S.A) and JEFF-3.0 (Europe)[1]. As a result, JENDL-3.3 yielded the keff values which were in better agreement with the experimental results than the other libraries. Additionally, it was found that the discrepancies of the keff values between JENDL-3.3 and the other libraries are mainly caused by the slight difference of the neutron capture cross section of carbon at 0.0253eV among the libraries, and we had been focusing on the accuracy of this cross section as one of the important subjects for the improvement of the neutronics calculations for the HTGRs.
Page 3: JAEA-Conf 2011-002 Proceedings of t
Page 7: JAEA-Conf 2011-002 31. Preliminary
Page 12 and 13: 6.2 Measurement of neutron-induced
Page 14 and 15: This is a blank page.
Page 16 and 17: JAEA-Conf 2011-002 Table 1 Comparis
Page 18 and 19: JAEA-Conf 2011-002 (T1/2=8,900,000
Page 22 and 23: JENDL-3.3 showed better applicabili
Page 24 and 25: ENDF. Thus this cross section store
Page 26 and 27: Acknowledgement JAEA-Conf 2011-002
Page 28 and 29: In the MALIBU program, isotope conc
Page 30 and 31: some minor actinides. For major act
Page 32 and 33: JAEA-Conf 2011-002 code MVP-BURN an
Page 34 and 35: JAEA-Conf 2011-002 [3] Measurements
Page 36 and 37: 3.1 Experimental Set up JAEA-Conf 2
Page 38 and 39: References JAEA-Conf 2011-002 [1] N
Page 40 and 41: JAEA-Conf 2011-002 was large. The a
Page 42 and 43: JAEA-Conf 2011-002 4. Results and D
Page 44 and 45: Acknowledgments Present study inclu
Page 46 and 47: Fig. 1 A conceptural picture of the
Page 48 and 49: 4. Theoretical studies Theoretical
Page 50 and 51: JAEA-Conf 2011-002 Fig.9 Comparison
Page 52 and 53: Ion source JAEA-Conf 2011-002 LE
Page 54 and 55: JAEA-Conf 2011-002 3. Readiness
Page 56 and 57: JAEA-Conf 2011-002
Page 58 and 59: JAEA-Conf 2011-002 Figure 1. An exa
Page 60 and 61: JAEA-Conf 2011-002 Figure 6. Compar
Page 62 and 63: JAEA-Conf 2011-002 calculation of d
Page 64 and 65: JAEA-Conf 2011-002 equilibrium emis
Page 66 and 67: JAEA-Conf 2011-002 Cowley et al. [1
Page 68 and 69: 4. Conclusions We have compared nuc
Page 70 and 71:
of MeV region with highest cosmic-r
Page 72 and 73:
JAEA-Conf 2011-002 events can be id
Page 74 and 75:
JAEA-Conf 2011-002 models and its p
Page 76 and 77:
JAEA-Conf 2011-002
Page 78 and 79:
JAEA-Conf 2011-002
Page 80 and 81:
JAEA-Conf 2011-002 xx
Page 82 and 83:
JAEA-Conf 2011-002 1. The recent ac
Page 84 and 85:
JAEA-Conf 2011-002 4. Conceptual de
Page 86 and 87:
This is a blank page.
Page 88 and 89:
The Institute's staff of about 280
Page 90 and 91:
3. Nuclear Theory Laboratory JAEA-C
Page 92 and 93:
JAEA-Conf 2011-002 References [1] P
Page 94 and 95:
JAEA-Conf 2011-002 reaction 6 Li +
Page 96 and 97:
Using the approximated distribution
Page 98 and 99:
Page 100 and 101:
momentum of the constituents of P.
Page 102 and 103:
dσ/dΩ (mb/sr) c.m. scattering ang
Page 104 and 105:
JAEA-Conf 2011-002 [2] N. Austern,
Page 106 and 107:
moderating fast neutrons emitted fr
Page 108 and 109:
JAEA-Conf 2011-002 3. Results and d
Page 110 and 111:
JAEA-Conf 2011-002 the detection de
Page 112 and 113:
Fig.1. Experimental arrangement for
Page 114 and 115:
in this work was confirmed. (2) 153
Page 116 and 117:
Neutron Capture Cross Section of 15
Page 118 and 119:
ENDF resonance parameters are based
Page 120 and 121:
sample changer. The measured flux s
Page 122:
REFERENCES JAEA-Conf 2011-002 [1] W
Page 125 and 126:
JAEA-Conf 2011-002 Fig. 4: The rela
Page 127:
Fig. 10: The PHITS2 calculation geo
Page 130 and 131:
for such a low energy region should
Page 132 and 133:
MCNPX calculation was performed bas
Page 134 and 135:
JAEA-Conf 2011-002 We measured dou
Page 136 and 137:
1mm-thick carbon target 22mm in dia
Page 138 and 139:
JAEA-Conf 2011-002 Figure 2 shows e
Page 140 and 141:
The double-differential (n,xp) and
Page 142 and 143:
JAEA-Conf 2011-002 forward angles.
Page 144 and 145:
Fig.3. Two-dimensional plot of PI v
Page 146 and 147:
JAEA-Conf 2011-002 Fig. 7. Deuteron
Page 148 and 149:
JAEA-Conf 2011-002 The new detector
Page 150 and 151:
4. Off line data analysis Double di
Page 152 and 153:
eports of data of carbon-ion incide
Page 154 and 155:
Count [-] 4 10 3 10 2 10 10 1 Charg
Page 156 and 157:
Acknowledgement We are grateful to
Page 158 and 159:
Beam Line BM1 Copper Target BM2 5×
Page 160 and 161:
φ = φbm · ρtof · ρmulti (2) E
Page 162 and 163:
References [1] K. Ishibashi, H. Tak
Page 164 and 165:
JAEA-Conf 2011-002 hint at the orig
Page 166 and 167:
Neutron Dose Rate [Sv/hr/src neutro
Page 168 and 169:
JAEA-Conf 2011-002 radiation protec
Page 170 and 171:
Ztarget, Atarget are the numbers fo
Page 172 and 173:
We described our formalism for calc
Page 174 and 175:
2. Model
Page 176 and 177:
JAEA-Conf 2011-002
Page 178 and 179:
JAEA-Conf 2011-002
Page 180 and 181:
JAEA-Conf 2011-002 reactions. Figur
Page 182 and 183:
JAEA-Conf 2011-002 Fig. 3. The angu
Page 184 and 185:
Page 186 and 187:
JAEA-Conf 2011-002
Page 188 and 189:
JAEA-Conf 2011-002
Page 190 and 191:
JAEA-Conf 2011-002
Page 192 and 193:
analysis of integral experiments [6
Page 194 and 195:
A modified SRAC library was prepare
Page 196 and 197:
JAEA-Conf 2011-002 approximately 0.
Page 198 and 199:
JAEA-Conf 2011-002 constructing the
Page 200 and 201:
Fig.9 Spectrum of gamma-ray followi
Page 202 and 203:
Page 204 and 205:
JAEA-Conf 2011-002 in the same way
Page 206 and 207:
JAEA-Conf 2011-002 [7]. For example
Page 208 and 209:
Page 210 and 211:
JAEA-Conf 2011-002 For
Page 212 and 213:
JAEA-Conf 2011-002
Page 214 and 215:
JAEA-Conf 2011-002
Page 216 and 217:
JAEA-Conf 2011-002 (5.0-9.0MeV), a
Page 218 and 219:
components, the 0.56Wt% for hydroge
Page 220 and 221:
Page 222 and 223:
Sensitivities of curium isotope con
Page 224 and 225:
decreases of (n,g) reaction rates,
Page 226 and 227:
5. Conclusion JAEA-Conf 2011-002 Wi
Page 228 and 229:
2. Foundation of sensitivity analys
Page 230 and 231:
JAEA-Conf 2011-002 where f g and f
Page 232 and 233:
Fig.1 Sensitivity coefficient of th
Page 234 and 235:
An outline of core configurations o
Page 236 and 237:
0.010% 0.000% -0.010% -0.020% -0.03
Page 238 and 239:
To clarify what nuclides and reacti
Page 240 and 241:
Calculation was performed by the MV
Page 242 and 243:
among these libraries, and the diff
Page 244 and 245:
Page 246 and 247:
JAEA-Conf 2011-002
Page 248 and 249:
JAEA-Conf 2011-002
Page 250 and 251:
JAEA-Conf 2011-002
show all

JAEA-Conf 2011-002 - 日本原子力研究開発機構

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?