Nuclear Design of the High-Temperature Engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, S.; Fujimoto, Nozomu; Takeda, Takeshi

doi:10.13182/nse96-a24156

Cited by 39 publications

(5 citation statements)

References 5 publications

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“…The nuclear determine calculation code system for the HTTR [8] consist of the computer codes DELIGHT, TWOTRAN-2 and CITATION-1000VP. The program structure of the system is shown in Fig.…”

Section: Evaluation Of Test Data 321 Calculation Methodsmentioning

confidence: 99%

Icone23-1130 Burn-Up Dependency of Control Rod Position at Zero Power Criticality in the High Temperature Test Engineering Reactor

Honda

Fujimoto

Sawahata

et al. 2015

ICONE

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The High Temperature Engineering Test Reactor (HTTR) is a block type fuel High Temperature Gas-cooled Reactor (HTGR) constructed in Japan, firstly. The operating data of the HTTR with burn-up is very important for developments of HTGRs. Many test data have been collected in the HTTR. Many tests are carried out in low power operation. On the other hand, the full power operation is not enough. There is a temperature distribution in a core in full power operation. The temperature distribution in a core makes it difficult to validate the calculation code. Additionally, it is difficult to measure core temperature in HTTR. On the other hands, the data of the control rod position at criticality at zero power have been measured at the beginning of each operation cycle and the temperature distribution in a core at zero power is uniform. Therefore, the data at zero power are suitable for confirm the characteristics of burn-up and validation of calculation code. In this study, the calculated control rod positions at zero power criticality with burn-up are compared with the experimental data with correlation of core temperature. The calculated results of criticality control rod position at zero power show good agreement to the experimental data. It means that calculated result shows appropriate decrease in uranium and accumulation in plutonium decrease in burnable absorber with burn-up.

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“…The nuclear determine calculation code system for the HTTR [8] consist of the computer codes DELIGHT, TWOTRAN-2 and CITATION-1000VP. The program structure of the system is shown in Fig.…”

Section: Evaluation Of Test Data 321 Calculation Methodsmentioning

confidence: 99%

Icone23-1130 Burn-Up Dependency of Control Rod Position at Zero Power Criticality in the High Temperature Test Engineering Reactor

Honda

Fujimoto

Sawahata

et al. 2015

ICONE

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“…The UFFM was installed in the High Temperature Engineering Test Reactor at the Japan Atomic Energy Research Institute. 5 It employs pairs of neutron and γ detectors to monitor the movement of fresh mixed-oxide fuel (MOX) assemblies between the core and fuel storage pool. The combination of neutron and γ ray signatures characterizes the transferred material as fresh fuel, spent fuel, or some other material.…”

Section: Unattended Fuel Flow Monitor (Uffm)mentioning

confidence: 99%

Radiation-Triggered Surveillance for UF6 Monitoring

Curtis

2015

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“…In the present analysis, the cell calculation is performed for the fuel cell, like the HTTR of JAERI (Yamashita et al, 1996). This fuel cell geometry is shown in Fig.…”

Section: Double Heterogeneity Cell Calculationmentioning

confidence: 99%

“…These parameters without the core height are based on HTTR (Yamashita et al, 1996). The ideal CANDLE burnup is realized for the infinite length of the core height.…”

Section: Calculation Conditionsmentioning

confidence: 99%