Evaluation of Fuel Temperature on High Temperature Test Operation at High Temperature Gas-Cooled Reactor 'HTTR'

Tochio, Daisuke; Sumita, Junya; Takada, Eiji; Fujimoto, Nozomu; Nakagawa, Shigeaki

doi:10.3327/taesj2002.5.57

Cited by 4 publications

(5 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Based on the data obtained by the rise-to-power tests of the HTTR up to an outlet coolant temperature of 850 • C [11], the systematic factors of the hot spot factors and analysis conditions were re-evaluated. The systematic factors related to thermal power, axial power distribution, and flow rate distribution; and the analysis conditions related to inlet coolant temperature, primary coolant flow rate, control rod position, and effective full-power days were revised [5,12]. Table 2 shows the revised systematic factors.…”

Section: Estimation Of Maximum Fuel Temperature 41 Revision Of Systmentioning

confidence: 99%

“…In addition, for every fuel column, only the fuel temperature of one fuel rod group, in which the appearance of the maximum fuel temperature was expected on the basis of the power density distribution obtained by the nuclear design, was calculated. Then, a detailed realistic core-shaped model was constructed as follows [12]:…”

Section: Improvement Of Analysis Modelsmentioning

confidence: 99%

“…• According to the above model update, power density distribution for every fuel rod was calculated by the continuous-energy Monte Carlo code MVP [13]. This nuclear calculation provides the reduction of the material heterogeneous effect factor for power density distribution from 1.07 to 1.0 [12].…”

Section: Improvement Of Analysis Modelsmentioning

confidence: 99%

See 2 more Smart Citations

Evaluation of maximum fuel temperature in HTTR

Inaba

Tochio

Ueta

et al. 2014

Journal of Nuclear Science and Technology

Self Cite

View full text Add to dashboard Cite

In order to ensure the thermal integrity of fuel in the high temperature engineering test reactor (HTTR), it is necessary that the maximum fuel temperature in the normal operation is to be lower than a thermal design limit of 1495 • C. In the core thermal and hydraulic design of the HTTR, the maximum fuel temperature was estimated to be 1492 • C, which satisfied the thermal design limit. However, the estimated temperature was derived by using hot spot factors with a large safety margin for the consideration of uncertainties in the design stage without the HTTR practical operating data, and thus there is no doubt that the estimated temperature includes excessive conservativeness. In order to obtain the maximum fuel temperature with appropriate conservativeness, the maximum fuel temperature has been re-evaluated on the basis of the HTTR operating data. In this paper, the random factors of the hot spot factors are revised by using the HTTR first fuel fabrication data, and the new maximum fuel temperature is estimated. As a result, the estimated maximum fuel temperature can be reduced to 1424 • C. The reduction of the maximum fuel temperature leads to a larger thermal margin in nuclear and fuel designs.

show abstract

Section: Estimation Of Maximum Fuel Temperature 41 Revision Of Systmentioning

confidence: 99%

Section: Improvement Of Analysis Modelsmentioning

confidence: 99%

See 1 more Smart Citation

Evaluation of maximum fuel temperature in HTTR

Inaba

Tochio

Ueta

et al. 2014

Journal of Nuclear Science and Technology

Self Cite

View full text Add to dashboard Cite

show abstract

“…A test plan of surveillance test is described in Section 5. A cumulative fast neutron fluence and temperature of fuel block estimated on the basis of the neutronic and temperature calculation are also given in Table 4 [16][17][18]. It was assumed that fast neutron fluence and temperature in each fuel block were equally distributed.…”

Section: Methodsmentioning

confidence: 99%

Investigation on structural integrity of graphite component during high temperature 950 °C continuous operation of HTTR

Sumita

Shimazaki

Shibata

2014

Journal of Nuclear Science and Technology

Self Cite

View full text Add to dashboard Cite

Graphite material is used for internal structures in high temperature gas-cooled reactor. The core components and graphite core support structures are so designed as to maintain the structural integrity to keep core cooling capability. To confirm that the core components and graphite core support structures satisfy the design requirements, the temperatures of the reactor internals are measured during the reactor operation. Surveillance test of graphite specimens and in-service inspection using TV camera are planned in conjunction with the refueling. This paper describes the evaluation results of the integrity of the core components and graphite core support structures during the high temperature 950• C continuous operation, a high temperature continuous operation with reactor outlet temperature of 950• C for 50 days, in high temperature engineering test reactor. The design requirements of the core components and graphite core support structures were satisfied during the high temperature 950• C continuous operation. The dimensional change of graphite which directly influences the temperature of coolant was estimated considering the temperature profiles of fuel block. The magnitude of irradiation-induced dimensional change considering temperature profiles was about 1.2 times larger than that under constant irradiation temperature of 1000• C. In addition, the programs of surveillance test and ISI using TV camera were introduced.

show abstract

“…Since the first criticality, several operations have been carried out, such as the ride-to-power tests [3], safety demonstration [4][5][6] and high-temperature long-term continuing operation tests [7].…”

Section: Introductionmentioning

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

View full text Add to dashboard Cite

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.

show abstract

Evaluation of Fuel Temperature on High Temperature Test Operation at High Temperature Gas-Cooled Reactor 'HTTR'

Cited by 4 publications

References 0 publications

Evaluation of maximum fuel temperature in HTTR

Evaluation of maximum fuel temperature in HTTR

Investigation on structural integrity of graphite component during high temperature 950 °C continuous operation of HTTR

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

Contact Info

Product

Resources

About