Measurement and analysis of low energy neutron spectrum in a large cylindrical iron assembly bombarded by D-T neutrons

Konno, Chikara; Ikeda, Yujiro; Kosako, Kazuaki; Oyama, Y.; Maekawa, Hiroshi; Nakamura, Tomoo; Bennett, E.F.

doi:10.1016/0920-3796(91)90142-d

Cited by 16 publications

(7 citation statements)

References 2 publications

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“…15 that the JENDL-3.3 calculations reproduce the measured spectra better than those of ENDF/B-VI. Figure 16 shows a comparison of the calculations with the neutron spectra measured 112) at 61 cm penetration from a large iron cylinder at JAERI FNS. JENDL-3.3 well reproduces the measured neutron spectra except for the energy re- 17 Comparison of benchmark calculations with the gamma-ray spectra measured at KfK gion between 0.7 and 1.0 MeV, where both the JENDL-3.3 and JENDL-3.2 calculations show slight underestimation as compared with the measurements.…”

Section: Shieldingmentioning

confidence: 99%

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.

Shibata

Kawano

Nakagawa

et al. 2002

J. Nucl. Sci. Technol.

463

306

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Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 235 U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

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Section: Shieldingmentioning

confidence: 99%

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.

Shibata

Kawano

Nakagawa

et al. 2002

J. Nucl. Sci. Technol.

463

306

View full text Add to dashboard Cite

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“…The experimental data and the calculation geometry of the integral experiment on the iron cylindrical assembly at the FNS were compiled in the SINBAD abstract NEA-1553/45 (Kodeli et al, 2006;NEA, 2022a;ORNL, 2022). The experiment was done in the first target room of the FNS facility of JAERI (Konno et al, 1991;Sub Working Group of Fusion Reactor Physics Subcommittee, 1994). Neutrons were produced by D-T nuclear reaction.…”

Section: Integral Experiments On Iron Cylindrical Assembly At Fnsmentioning

confidence: 99%

“…Fusion neutron engineering research began in Japan in the early 1980s. The highintensity D-T neutron facilities, i.e., the Fusion Neutronics Source (FNS) at the Japan Atomic Energy Research Institute (JAERI, now the Japan Atomic Energy Agency) and the OKTAVIAN at Osaka University, are the world's leading facilities providing experimental data related to fusion research (Konno et al, 1991;Sub Working Group of Fusion Reactor Physics Subcommittee, 1994). Fundamental integral benchmark experiments were performed in these facilities for fusion applications.…”

Section: Introductionmentioning

confidence: 99%

“…This paper is organized as follows. Section 2 presents experimental and calculation conditions of two experiments related with fusion and three experiments related with acceleratorshielding, which were generated from (1) Integral experiment on iron cylindrical assembly with D-T neutron source at FNS (Konno et al, 1991;Sub Working Group of Fusion Reactor Physics Subcommittee, 1994), (2) Leakage neutron spectra from various sphere piles with D-T neutron source at OKTAVIAN, Osaka university (Sub Working Group of Fusion Reactor Physics Subcommittee, 1994), (3) Neutron energy spectra after transmission through shields using a quasi-monochromatic neutron source at TIARA (Nakao et al, 1996;Nakashima et al, 1996), (4) Thick target neutron yield produced by high-energy heavy-ion incident reaction at HIMAC (Kurosawa et al, 1999;Satoh et al, 2007), and (5) Induced activity in shield exposed to particles produced by heavy-ion on Fe at HIMAC (Ogawa et al, 2011). For the cases of (3), (4), and (5), the benchmark studies have been conducted in our previous paper and report (Ogawa et al, 2011;NEA, 2022b;Iwamoto et al, 2022).…”

Section: Introductionmentioning

confidence: 99%

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Benchmark shielding calculations for fusion and accelerator-driven sub-critical systems

Iwamoto

Tsuda²,

Ogawa³

2023

Front. Energy Res.

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We conducted benchmark calculations of neutron-shielding experiments for fusion applications such as (1) Neutron spectra in iron shields with 14 MeV neutrons; and (2) Leakage neutron spectra from various sphere piles by 14 MeV neutrons, and for Accelerator-Driven Sub-Critical system (ADS) such as (3) Neutron energy spectra after transmission through iron and concrete shields using a quasi-monochromatic neutron source, (4) Thick target neutron yield produced by high-energy heavy ion incidence on a thick target, and (5) Induced radio activity in concrete exposed to secondary particles produced by heavy-ion incident reaction on an iron target by using the Particle and Heavy Ion Transport code System (PHITS). For case (1), the calculated neutron energy spectra using the nuclear data libraries, JENDL-4.0, agreed with the experimental data in iron shields. For the cases (2) of Al, Ti, Cr, and As piles, the neutron energy spectra calculated with JENDL-4.0 agreed with the experimental results well. For the case (3), the neutron spectra calculated with JENDL-4.0/HE reproduced the experimental data because the proton data library of 7Li can produce source neutrons for proton incident reactions. For the case (4), calculated results for thick target neutron spectra produced by a 400 MeV per nucleon carbon incident reaction on lead reproduced the experimental data well. For the case (5) with a neutron source produced by the 200–400 MeV per nucleon heavy-ion incident reaction, the calculated results of the reaction rate depth profiles of 197Au (n, γ)198Au reactions reproduced the experimental results within a factor of 2. Overall, PHITS with nuclear data libraries reproduced the experimental data sufficiently well. Thus, PHITS has a potential application in the design of advanced reactor systems, such as fusion and ADS facilities. This experimental data are also useful in validating nuclear reaction models in other Monte Carlo codes and evaluating nuclear data libraries for advanced reactor systems.

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“…15 that the JENDL-3.3 calculations reproduce the measured spectra better than those of ENDF/B-VI. Figure 16 shows a comparison of the calculations with the neutron spectra measured 112) at 61 cm penetration from a large iron cylinder at JAERI FNS. JENDL-3.3 well reproduces the measured neutron spectra except for the energy re- Figure 17 compares the calculations with the gammaray spectra from an iron sphere with a 252 Cf source in the center measured 113) at KfK.…”

Section: Shieldingmentioning

confidence: 99%