JAEA-Conf 2011-002 - 日本原子力研究開発機構

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JENDL-3.3 showed better applicability to the HTTR criticality calculations than the other libraries as mentioned above, but still overestimated the keff values by 0.5-1.1%k. Overestimating the keff values, the calculation result of the loaded number of the fuel columns achieving the first criticality did not agree with the experimental results. These problems has not been resolved until today, despite our efforts of the refinement such as the description of the core geometry and the concentration of the components. Meanwhile, the neutron capture cross section of carbon at 0.0253eV stored in each nuclear data library had not been revised for a long time. Thus we proposed this cross section should be revised based on the latest measurement data, and also predicted that the problem of overestimating the keff values will be resolved by revising the cross section to be about 10% larger than that of JENDL-3.3. In May 2010, the latest JENDL: JENDL-4.0[2], was released by JAEA. In JENDL-4.0, our proposal and prediction were applied, and the neutron capture cross section of carbon at 0.0253eV was revised based on the latest measurement data[3]. Accordingly the problem of overestimating the keff values in the HTTR criticality calculations was expected to be improved. This paper describes the investigation of the applicability of JENDL-4.0 to the HTTR criticality calculations. 2. Calculations for HTTR critical approach with JENDL-4.0 2.1 Objective and method The objective of this study is to investigate the applicability of JENDL-4.0 to the HTTR criticality calculations. The investigation was performed by comparing (a)The loaded number of fuel columns achieving the first criticality, and (b)Excess reactivity of the fully loaded core, between the experimental results and the calculation results with several nuclear data libraries, which are JENDL-4.0, previous JENDL: JENDL-3.3, the latest ENDF: ENDF/B-VII.0, and the latest JEFF: JEFF-3.1. Additionally, identification of nuclides which have large effects on the difference of the following issues among the libraries was studied. 2.2 HTTR critical approach JAEA-Conf 2011-002 (1) HTTR The HTTR is a graphite-moderated and helium gas-cooled block-type HTGR, situated at JAEA-Oarai Resarch and Development Center. It has 30MW thermal power and its outlet coolant temperature, which can be used for nuclear heat utilization, is 850C in rated power operation. Additionally, the HTTR can also be operated in high temperature test operation mode, with which its outlet coolant temperature is 950C. Figure 1 shows radial and bird-eye views of the HTTR core. The core is constructed by stacking four kinds of hexagonal blocks, which are fuel blocks, control rod guide blocks, replaceable reflector blocks and irradiation blocks (for irradiation test), and is surrounded by permanent reflectors made of graphite. All these hexagonal blocks are made of high-purity graphite, and are the same in across flats (36cm) and height (58cm). Fuel region in the core is composed of 30 fuel columns, in which five fuel blocks are stacked.
(2) Critical approach CRs insertion hole The critical approach of the HTTR was carried out by the BP fuel addition method at room 58cm 1st layer 2nd layer temperature. In the critical 3rd layer approach, dummy graphite 36cm 4th layer blocks previously placed in the core were replaced with fresh 5th layer fuel blocks from the outer core Permanent reflector region in the form of fuel Fuel block columns as shown in Fig. 2. The Replaceable reflector block Fuel block first criticality was achieved by CRs guide block Reflector block, CRs guide block or an annular form core Irradiation block Irradiation block comprising 19 fuel columns. After the first criticality, the fuel Fig. 1 Schematic diagram of HTTR core loading was carried out additionally to construct the fully loaded core at room temperature. The fully loaded core was constructed by a cylindrical form core comprising 30 fuel columns. Fuel Fuel block block Replaceable reflector block Control rod guide block Irradiation block JAEA-Conf 2011-002 Dummy graphite block Initial 12 fuel column loaded core 19 fuel column loaded core 30 fuel column loaded core (Full loaded core core Fig. 2 Procedure of HTTR critical approach Center of the core 2.3 Neutron capture cross section of carbon at 0.0253eV stored in each libraries Table 1 shows the neutron capture cross section of carbon at 0.0253eV stored in the each libraries. In JENDL-4.0, the cross section was revised to 3.85mb, which is 9% larger than JENDL-3.3 and is 15% larger than ENDF/B-VII.0 and JEFF-3.1. The neutron capture cross section of carbon at 0.0253eV of JENDL-3.3 was taken from JENDL-3[4], which was released in 1989, and therefore this cross section stored in JENDL had not been revised for 21 years. Meanwhile the cross section of ENDF/B-VII.0 is taken from ENDF/B-IV[5,6], which was released in 1974, or might be taken from more previous version of Fuel region
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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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JAEA-Conf 2011-002 Fig. 3. The angu
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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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