Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions

Reactor pressure vessel (RPV) support is a key safety facility which is categorized as Class 1 in the ASME nuclear safety design. The temperature distribution of RPV support is one of the key considerations for the concrete safety contacting with the bottom of the support. So it is necessary for acc...

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Main Authors: Longkun He, Ying Lv, Pengfei Liu
Format: Article
Language:English
Published: Hindawi Limited 2019-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2019/1217073
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spelling doaj-866c04bdb2e145c19ebea5a6ce362f402020-11-24T22:11:28ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832019-01-01201910.1155/2019/12170731217073Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating ConditionsLongkun He0Ying Lv1Pengfei Liu2School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, ChinaShanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai 200233, ChinaSchool of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, ChinaReactor pressure vessel (RPV) support is a key safety facility which is categorized as Class 1 in the ASME nuclear safety design. The temperature distribution of RPV support is one of the key considerations for the concrete safety contacting with the bottom of the support. So it is necessary for accurate evaluation on the temperature field characteristics of RPV support, especially the bottom of support. This paper investigates the temperature field characteristics of modified RPV support which will be applied to a large advanced pressurized water reactor. A support entity is manufactured in a ratio of 1:1, and its temperature distribution is measured under simulated reactor operating conditions. Numerical simulation is also used to validate the results by the developed CFD model. The results show that under the operating conditions, of which the inlet cooling air temperature is 35.35°C and the velocity is 6.25 m/s, the temperature distribution of modified RPV support bottom is uneven, and the highest temperature is around 38°C, which is much lower than the demanding design temperature 93.3°C. Therefore, the design of the modified RPV support is reliable. In addition, the results of numerical simulation agree well with the experimental results with the error less than ±4°C, which ensures the reliability of the conclusion. The effects of inlet cooling air temperature and velocity on the RPV support temperature distribution are further studied. Both the temperature decrease and velocity increase can reduce the RPV support temperature. But the effect of inlet cooling air temperature is more obvious than inlet cooling air velocity. So the best way to improve air cooling capacity is to decrease the support inlet cooling air temperature. The results can provide a good guidance to the design of RPV support for the subsequent large advanced pressurized water reactor.http://dx.doi.org/10.1155/2019/1217073
collection DOAJ
language English
format Article
sources DOAJ
author Longkun He
Ying Lv
Pengfei Liu
spellingShingle Longkun He
Ying Lv
Pengfei Liu
Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions
Science and Technology of Nuclear Installations
author_facet Longkun He
Ying Lv
Pengfei Liu
author_sort Longkun He
title Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions
title_short Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions
title_full Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions
title_fullStr Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions
title_full_unstemmed Experimental and Numerical Investigation of Temperature Distribution on Reactor Pressure Vessel Support under Operating Conditions
title_sort experimental and numerical investigation of temperature distribution on reactor pressure vessel support under operating conditions
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2019-01-01
description Reactor pressure vessel (RPV) support is a key safety facility which is categorized as Class 1 in the ASME nuclear safety design. The temperature distribution of RPV support is one of the key considerations for the concrete safety contacting with the bottom of the support. So it is necessary for accurate evaluation on the temperature field characteristics of RPV support, especially the bottom of support. This paper investigates the temperature field characteristics of modified RPV support which will be applied to a large advanced pressurized water reactor. A support entity is manufactured in a ratio of 1:1, and its temperature distribution is measured under simulated reactor operating conditions. Numerical simulation is also used to validate the results by the developed CFD model. The results show that under the operating conditions, of which the inlet cooling air temperature is 35.35°C and the velocity is 6.25 m/s, the temperature distribution of modified RPV support bottom is uneven, and the highest temperature is around 38°C, which is much lower than the demanding design temperature 93.3°C. Therefore, the design of the modified RPV support is reliable. In addition, the results of numerical simulation agree well with the experimental results with the error less than ±4°C, which ensures the reliability of the conclusion. The effects of inlet cooling air temperature and velocity on the RPV support temperature distribution are further studied. Both the temperature decrease and velocity increase can reduce the RPV support temperature. But the effect of inlet cooling air temperature is more obvious than inlet cooling air velocity. So the best way to improve air cooling capacity is to decrease the support inlet cooling air temperature. The results can provide a good guidance to the design of RPV support for the subsequent large advanced pressurized water reactor.
url http://dx.doi.org/10.1155/2019/1217073
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AT pengfeiliu experimentalandnumericalinvestigationoftemperaturedistributiononreactorpressurevesselsupportunderoperatingconditions
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