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JAEA Reports

Estimation of exchange time for neutron startup sources of HTTR

Ono, Masato; Kozawa, Takayuki; Fujimoto, Nozomu*

JAEA-Technology 2019-012, 15 Pages, 2019/09

JAEA-Technology-2019-012.pdf:2.83MB

The High Temperature Engineering Test Reactor has a neutron source of $$^{252}$$Cf to start up the reactor and to confirm count rates of wide range monitors. The half-life of $$^{252}$$Cf is short, about 2.6 years, so it is necessary to replace at an appropriate time. In order to estimate the period to replace, it is necessary to consider not only the half-life but also the fluctuation of the count rate of the wide range monitor to prevent alarm. For that reason, the method has been derived to predict a minimum count rate from relationship between the count rate and the standard deviation of the count rate of the wide range monitors. As a result of predicting the count rate using this method, it was found that the minimum count rate reaches to 3.0cps in 2022 and 1.5 cps in 2024. Therefore, it is necessary to exchange $$^{252}$$Cf by 2024.

Journal Articles

Improvement of neutron startup source handling work by developing new transportation container for High-Temperature engineering Test Reactor (HTTR)

Shimazaki, Yosuke; Sawahata, Hiroaki; Shinohara, Masanori; Yanagida, Yoshinori; Kawamoto, Taiki; Takada, Shoji

Journal of Nuclear Science and Technology, 54(2), p.260 - 266, 2017/02

 Times Cited Count:2 Percentile:19.65(Nuclear Science & Technology)

The High-Temperature engineering Test Reactor (HTTR) has three neutron startup sources (NSs) in the reactor core, each of which consists of $$^{252}$$Cf with 3.7 GBq and is contained in a small capsule, installed in NS holder and subsequently in a control guide block (CR block). The NSs are exchanged at the interval of approximately 7 years. The NS holders are transported from the dealer's hot cell to the reactor facility of HTTR using a transportation container. The loading work of NS holders to the CR blocks is subsequently carried out in the fuel handling machine maintenance pit of HTTR. Technical issues, which are the reduction and prevention of radiation exposure of workers and the exclusion of falling of NS holder, were extracted from the experiences in past two exchange works of NSs to develop a safety handling procedure. Then, a new transportation container special to the NSs of HTTR was developed to solve the technical issues while keeping the cost as low as that for overhaul of conventional container. As the results, the NS handling work using the new transportation container was safely accomplished by developing the new transportation container which can reduce the risks of radiation exposure dose of workers and exclude the falling of NS holder.

JAEA Reports

Shielding calculation by PHITS code during replacement works of startup neutron sources for HTTR operation

Shinohara, Masanori; Ishitsuka, Etsuo; Shimazaki, Yosuke; Sawahata, Hiroaki

JAEA-Technology 2016-033, 65 Pages, 2017/01

JAEA-Technology-2016-033.pdf:11.14MB

To reduce the neutron exposure dose for workers during the replacement works of the startup neutron sources of the High Temperature Engineering Test Reactor, calculations of the exposure dose in case of temporary neutron shielding at the bottom of fuels handling machine were carried out by the PHITS code. As a result, it is clear that the dose equivalent rate due to neutron radiation can be reduced to about an order of magnitude by setting a temporary neutron shielding at the bottom of shielding cask for the fuel handling machine. In the actual replacement works, by setting temporary neutron shielding, it was achieved that the cumulative equivalent dose of the workers was reduced to 0.3 man mSv which is less than half of cumulative equivalent dose for the previous replacement works; 0.7 man mSv.

Journal Articles

Development of transportation container for the neutron startup source of High Temperature engineering Test Reactor (HTTR)

Shimazaki, Yosuke; Ono, Masato; Tochio, Daisuke; Takada, Shoji; Sawahata, Hiroaki; Kawamoto, Taiki; Hamamoto, Shimpei; Shinohara, Masanori

Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.1034 - 1042, 2016/03

In High Temperature Engineering Test Reactor (HTTR), three neutron holders containing $$^{252}$$Cf with 3.7 GBq for each are loaded in the graphite blocks and inserted into the reactor core as a neutron startup source which is changed at the interval of approximately ten years. These neutron holders containing the neutron sources are transported from the dealer's hot cell to HTTR using the transportation container. The holders loading to the graphite block are carried out in the fuel handling machine maintenance pit of HTTR. There were two technical issues for the safety handling work of the neutron holder. The one is the radiation exposure caused by significant movement of the container due to an earthquake, because the conventional transportation container was so large ($$phi$$1240 mm, h1855 mm) that it can not be fixed on the top floor of maintenance pit by bolts. The other is the falling of the neutron holder caused by the difficult remote handling work, because the neutron holder capsule was also so long ($$phi$$155 mm, h1285 mm) that it can not be pulled into the adequate working space in the maintenance pit. Therefore, a new and low cost transportation container, which can solve the issues, was developed. To avoid the neutron and $$gamma$$ ray exposure, smaller transportation container ($$phi$$820mm, h1150 mm) which can be fixed on the top floor of maintenance pit by bolts was developed. In addition, to avoid the falling of the neutron holder, smaller neutron holder capsule ($$phi$$75 mm, h135 mm) with simple handling mechanism which can be treated easily by manipulator was also developed. As the result of development, the neutron holder handling work was safely accomplished. Moreover, a cost reduction for manufacturing was also achieved by simplifying the mechanism of neutron holder capsule and downsizing.

Journal Articles

$$^{1}S_{0}$$ proton superfluidity in neutron star matter; Impact of bulk properties

Tanigawa, Tomonori; Matsuzaki, Masayuki*; Chiba, Satoshi

Physical Review C, 70(6), p.065801_1 - 065801_7, 2004/12

 Times Cited Count:9 Percentile:51.36(Physics, Nuclear)

We study the $$^{1}S_{0}$$ proton pairing gap in neutron star matterputting emphasis on influence of the Dirac effective mass and theproton fraction on the gap within the relativistic Hartree-Bogoliubovmodel. The gap equation is solved using the Bonn-B potential as aparticle-particle channel interaction. It is found that the maximalpairing gap $$Delta_mathrm{max}$$ is 1-2MeV, which has a strongcorrelation with the Dirac effective mass. Hence we suggest that itserves as a guide to narrow down parameter sets of the relativisticeffective field theory. Furthermore, the more slowly protons increasewith density, the lower the peak of the gap and the wider thesuperfluid range become.

JAEA Reports

Neutron data storage and retrieval system NESTOR2

Nakagawa, Tsuneo

JAERI-Data/Code 2003-016, 89 Pages, 2003/11

JAERI-Data-Code-2003-016.pdf:3.0MB

The data storage and retrieval system for neutron-induced reaction data NESTOR2 was developed. NESTOR2 was written in Fortran77, and can be used on workstations with UNIX and personal computers with Windows. Input data to NESTOR2 are those in EXFOR which are compiled and maintained under the international collaboration for nuclear data. By using the retrieval code, they can obtain lists of data index, numerical data and comment information and data files of numerical data. The present report explains the system and provides a user's manual of NESTOR2.

Journal Articles

Possibility of $$LambdaLambda$$ pairing and its dependence on background density in a relativistic Hartree-Bogoliubov model

Tanigawa, Tomonori; Matsuzaki, Masayuki*; Chiba, Satoshi

Physical Review C, 68(1), p.015801_1 - 015801_8, 2003/07

 Times Cited Count:16 Percentile:68.45(Physics, Nuclear)

We calculate a $$LambdaLambda$$ pairing gap in binary mixed matter of nucleons and $$Lambda$$ hyperons within the relativistic Hartree-Bogoliubov model since a recent experiment suggests a weaker $$LambdaLambda$$ attraction than before, which has a significant impact on properties of neutron stars in various aspects. Lambda hyperons to be paired up are immersed in background nucleons in normal state. A phenomenological $$LambdaLambda$$ interaction, which is derived relativistically from the Lagrangian of the system, is adopted to the gap equation. It is found that at background density $$rho_{N}=2.5rho_{0}$$ the $$LambdaLambda$$ pairing gap is very small, and that denser background makes it rapidly suppressed. This result suggests a mechanism, specific to mixed matter dealt with relativistic models, of its dependence on the nucleon density.

JAEA Reports

Proceedings of the 3rd Symposium on Science of Hadrons under Extreme Conditions; January 29-31, 2001, JAERI, Tokai, Japan

Chiba, Satoshi

JAERI-Conf 2001-012, 116 Pages, 2001/09

JAERI-Conf-2001-012.pdf:6.33MB

The third symposium on Science of Hadrons under Extreme Conditions, organized by the Research Group for Hadron Science, Advanced Science Research Center, was held at Tokai Research Establishment of JAERI on January 29 to 31, 2001. The symposium was devoted for discussions and presentations of research results in wide variety of hadron physics such as nuclear matter, high-energy nuclear reactions, quantum chromodynamics, neutron stars,supernovae, nucleosynthesis as well as finite nuclei to understand various aspects of hadrons under extreme conditions. Twenty two papers on these topics, including a special talk on the present status of JAERI-KEK joint project on high-intentisy proton accelerator, presented at the symposium aroused lively discussions among approximately 40 participants.

JAEA Reports

Improvement of core calculation model of High Temperature Engineering Test Reactor; Related with excess reactivity

Fujimoto, Nozomu; Yamashita, Kiyonobu

JAERI-Research 99-059, p.43 - 0, 1999/11

JAERI-Research-99-059.pdf:2.51MB

no abstracts in English

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