JAEA-Conf 2011-002 - 日本原子力研究開発機構

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JAEA-Conf 2011-002 (T1/2=8,900,000 year) and 60 Fe (T1/2=1,500,000 year) might be considered, even though not included in Table 3. The Hf is used for control rods of BWR as a strong neutron absorber and the 182 Hf is produced by two step neutron capture reaction as 180 Hf (n,g) 181 Hf (n,g) 182 Hf. The 60 Fe is created by also two step capture reaction and decays to 60 Co! It should be also noted it is difficult to measure half-lives for these RIs accurately. Table 3 Nuclides Listed in Table 2 of IAEA Safety Guideline RS-G-1.7 3 H, 7 Be, 14 C, 18 F, 22,24 Na, 31 Si, 32,33 P, 35 S, 36,38 Cl, 42,43 K, 45,47 Ca, 46,47,48 Sc, 48 V, 51 Cr, 51,52,52m,53,54,56 Mn, 52,55,59 Fe, 55,56,57,58,58m,60,60m,61,62m Co, 59,63,65 Ni, 64 Cu, 65,69,69m Zn, 72 Ga, 71 Ge, 73,74,76,77 As, 75 Se, 82 Br, 86 Rb, 85,85m,87m,89,90,91,92 Sr, 90,91,91m,92,93 Y, 93,95,97 Zr, 93m,94,95,97,98 Nb, 90,93,99,101 Mo, 96,96m,97,97m,99,99m Tc, 97,103,105,106 Ru, 109,115,115m Cd, 111,113m,114m,115m In, 123m,125m,127,127m,129,129m,131,131m,132,133,133m,134 Te, 103m,105 Rh, 103,109 Pd, 105,110m,111 Ag, 113,125 Sn, 122,124,125 Sb, 123,125,126,129,130,131,132,133,134,135 I, 129,131,132,134,134m,135,136,137,138 Cs, 131,140 Ba, 140 La, 139,141,143,144 Ce, 142,143 Pr, 147,149 Nd, 147,149 Pm, 151,153 Sm, 152,152m,154,155 Eu, 153,159 Gd, 160 Tb, 165,166 Dy, 166 Ho, 169,171 Er, 170,171 Tm, 175 Yb, 177 Lu, 181 Hf, 182 Ta, 181,185,187 W, 186,188 Re, 185,191,191m,193 Os, 190,192,194 Ir, 191,193m,197,197m Pt, 198,199 Au, 197,197m,203 Hg, 200,201,202,204 Tl, 203 Pb, 206,207 Bi, 203,205,207 Po, 211 At, 225,227 Ra, 226,229 Th, 230,233 Pa, 230,231,232,233,236,237,239,240 U, 237,239,240 Np, 234,235,236,237,238,239,240,241,242,243,244 Pu, 241,242,242m,243 Am, 242,243,244,245,246,247,248 Cm, 249 Bk, 246,248,249,250,251,252,253,254 Cf, 253,254,254m Es, 254,255 Fm Under Line: Nuclides considered in the Japanese Clearance Regulation (+ 41 Ca, 44 Ti, 49 V, 67 Ga, 68 Ge, 81 Rb, 108m Ag, 133 Ba, 169 Yb, 188 W, 195 Au) Shielding calculation (radiation transport and deep penetration) is also needed for the human radiation protection. For this purpose, elastic scattering cross section and angular distribution, neutron disappearance cross section, nuclear structure and decay data are required. And also PKA and KERMA data with charged-particle spectra is needed for the dose evaluation as the Linear Energy Transfer (LET). 2.4 Nuclear Security and Forensics for Nuclear Non-proliferation The nuclear forensics and nuclear detection are necessary for the nuclear non-proliferation. The nuclear forensics is to determine the origin of fissionable materials, by analyzing isotope abundances, impurities, etc. with irradiation and/or mining histories. Nuclear data are needed for this irradiation history by estimating isotope productions. For nuclear detection, candidate techniques such as the Neutron Interrogation Method (NIM) and Laser-Induced Breakdown Plasma (LIBP) + Resonance Absorption Spectroscopy (RAS) are being developed. For these, neutron and photo fission cross sections, FPY, decay data and photonuclear reaction data are requested. The objective mentioned in this chapter can be achieved by producing JENDL General Purpose File, JENDL/HE, JENDL/PD and JENDL/PK. Furthermore, JENDL Activation File including RI production cross sections and FPY is required for the down-stream applications near future.
JAEA-Conf 2011-002 3. Perspective of Future Nuclear Data Activities The 2nd Period Mid-term Plan of JAEA (2010-2014) is “incident energy expansion of JENDL” for nuclear data to produce Intermediate Energy Files (JENDL/HE, JENDL/PD, etc.). For update of the general purpose file of JENDL (JENDL-4.1?), covariance data and quality assurance are also important. Furthermore, JENDL Activation File (JENDL/A) with error data is also mentioned above. To prepare and update nuclear data files, the development of original nuclear reaction model code is necessary for easily and timely nuclear data evaluation and/or improvement to meet user requirements. For this purpose, the code CCONE is the strong candidate. In the short period, the CCONE is planned to be improved by adding some models, such as multiple nucleon and light charged particle emissions from pre-equilibrium stage, to expand the incident energy region, and for unknown (at this moment) user needs. This improvement is also useful to prepare for the next generation. As the preparation for the next generation, some items related to nuclear data activities not only in Japan and also in the world stand on the edge of precipice. They are crisis of the human resources for nuclear data evaluation (especially for decay and nuclear structure data), the budget (especially for nuclear data measurements), and presence (appearing) to the stake-holders. Those should be considered as soon as possible so that nuclear data activity level is kept for next generations. To avoid the crisis of human resources, the urgent fostering talents (tutorials, production of textbook, etc.) are required for nuclear data producers, especially for the items of “Endangered Species” such as ENSDF evaluators, resonance analyzers, producers of the thermal scattering law, etc. And the next generation evaluators for fission reaction (neutron spectra, delayed neutron, FPY, etc.), light-mass nuclides and evaluation tool makers should also be considered. Collaborations with the people of nuclear physics fields such as fundamental theories, microscopic approaches are getting more important. To produce evaluated nuclear data file, the international collaborations and considering TENDL-like approaches might be necessary. Though the certain level budget is desired to keep measurement facilities for nuclear data, recently if faces to some difficulty. It is true that nuclear data is an item like air, however, producers cannot live on air. Here international collaborations to share the experiments into the several facilities like European example should be convinced urgently. For obtaining the budget, it is also important to show the presence of nuclear data with the impact to the stake-holders such as the government (both nuclear power developments and regulation sides), industry users and plant makers. 4. Summary The JENDL-4 has been released in 2010 as one of goals of the first period mid-term research plan for JAEA. In the plan for the second period, the objective is “incident energy expansion of JENDL”. The objective can be achieved by producing JENDL/HE, JENDL/PD, and JENDL/PK. For this purpose, CCONE is planned to be improved by adding some models. The nuclear data for the burn-up, activation, and PKA/DPA calculations will be prepared for the applications of reactors, safety research, material science, nuclear forensics, etc. The urgent problems for human resources, presence to the stake-holders, and budget should be solved for example, by efforts of the international collaborations, etc.
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4. Conclusions We have compared nuc
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of MeV region with highest cosmic-r
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JAEA-Conf 2011-002 events can be id
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JAEA-Conf 2011-002 models and its p
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JAEA-Conf 2011-002 1. The recent ac
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JAEA-Conf 2011-002 4. Conceptual de
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The Institute's staff of about 280
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3. Nuclear Theory Laboratory JAEA-C
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JAEA-Conf 2011-002 References [1] P
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JAEA-Conf 2011-002 reaction 6 Li +
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Using the approximated distribution
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momentum of the constituents of P.
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dσ/dΩ (mb/sr) c.m. scattering ang
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JAEA-Conf 2011-002 [2] N. Austern,
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moderating fast neutrons emitted fr
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JAEA-Conf 2011-002 3. Results and d
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JAEA-Conf 2011-002 the detection de
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Fig.1. Experimental arrangement for
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in this work was confirmed. (2) 153
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Neutron Capture Cross Section of 15
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ENDF resonance parameters are based
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sample changer. The measured flux s
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REFERENCES JAEA-Conf 2011-002 [1] W
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JAEA-Conf 2011-002 Fig. 4: The rela
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Fig. 10: The PHITS2 calculation geo
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for such a low energy region should
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MCNPX calculation was performed bas
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JAEA-Conf 2011-002 We measured dou
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1mm-thick carbon target 22mm in dia
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JAEA-Conf 2011-002 Figure 2 shows e
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The double-differential (n,xp) and
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JAEA-Conf 2011-002 forward angles.
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Fig.3. Two-dimensional plot of PI v
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JAEA-Conf 2011-002 Fig. 7. Deuteron
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JAEA-Conf 2011-002 The new detector
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4. Off line data analysis Double di
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eports of data of carbon-ion incide
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Count [-] 4 10 3 10 2 10 10 1 Charg
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Acknowledgement We are grateful to
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Beam Line BM1 Copper Target BM2 5×
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φ = φbm · ρtof · ρmulti (2) E
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References [1] K. Ishibashi, H. Tak
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JAEA-Conf 2011-002 hint at the orig
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Neutron Dose Rate [Sv/hr/src neutro
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JAEA-Conf 2011-002 radiation protec
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Ztarget, Atarget are the numbers fo
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We described our formalism for calc
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2. Model
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JAEA-Conf 2011-002 reactions. Figur
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analysis of integral experiments [6
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A modified SRAC library was prepare
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JAEA-Conf 2011-002 approximately 0.
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JAEA-Conf 2011-002 constructing the
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Fig.9 Spectrum of gamma-ray followi
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JAEA-Conf 2011-002 in the same way
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JAEA-Conf 2011-002 [7]. For example
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JAEA-Conf 2011-002 For
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JAEA-Conf 2011-002 (5.0-9.0MeV), a
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components, the 0.56Wt% for hydroge
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Sensitivities of curium isotope con
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decreases of (n,g) reaction rates,
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5. Conclusion JAEA-Conf 2011-002 Wi
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2. Foundation of sensitivity analys
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JAEA-Conf 2011-002 where f g and f
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Fig.1 Sensitivity coefficient of th
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An outline of core configurations o
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0.010% 0.000% -0.010% -0.020% -0.03
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To clarify what nuclides and reacti
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Calculation was performed by the MV
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among these libraries, and the diff
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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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