All Issue

2026 Vol.4, Issue 1 Preview Page

Research Article

Ultimate Pressure Capacity Evaluation of 1:4 Scale PHWR Reactor Containment Building Model

중수로형 원자로건물 1/4 축소모형의 극한내압능력 평가

Ii Hwan Moon1*
,
Ju Ram Kim2
,
Ju Yoon Kim3
문 일환1*
,
김 주람2
,
김 주윤3
1Professor, DNA+ Professional Graduate School of Technology, Daejin University, Pocheon 11159, Korea
2PhD Candidate, Department of Civil and Environmental Engineering, Kookmin University, Seoul 02707, Korea
3PhD Candidate, Department of Department of Civil and Environmental Engineering, Daejin University, Pocheon 11159, Korea
1대진대학교 DNA+ 기술전문대학원 교수
2국민대학교 건설환경공학과 박사과정
3대진대학교 토목환경공학과 박사과정
*Corresponding Author
30 June 2026. pp. 35-45
PDF XML Citation
Abstract

Test of 1:4 scale model of 540 MWe pressurized heavy water reactor (PHWR) containment building will be perfomed by India Bhabha Atomic Research Center sooner or later. This study is to evaluate ultimate state behavior of the PHWR containment test model. PHWR containment building is pre-stressed concrete structure with a bonded tendon system. and the inside surface of the structure is coated with epoxy. Two steam generator openings in dome along with main airlock, fuelling machine airlock and emergency airlock barrel openings in cylindrical wall are included in this structure, and that is designed for an internal pressure of 0.142 MPa. In this study, The PHWR containment building is idealized as a three-dimensional finite element model and a nonlinearity of the materials is considered for estimation of structural failure. This paper represents structural failure modes of the containment structure under high pressure, and summarizes the analysis result.

Keywords
PHWR containment building
bonded tendon system
structural failure mode
analysis result

인도 바바 원자력 연구소(BARC)에서는 조만간 540 MWe급 중수로(PHWR) 원자로건물의 1/4 축소모형에 대한 시험을 수행할 예정이다. 본 연구의 목적은 이러한 PHWR 격납건물 시험 모형의 극한 상태 거동을 평가하는 것이다. 해당 PHWR 원자로건물은 부착식 텐던 시스템을 갖춘 프리스트레스트 콘크리트 구조물이며, 구조물 내부 표면은 에폭시로 코팅되어 있다. 본 구조물은 돔 부위의 증기발생기 관통부 2개와 더불어 실린더 벽체의 main airlock(MAL), fuelling machine air lock(FMAL) 및 emergency air lock(EAL) 배럴 관통부를 포함하고 있으며, 0.142 MPa의 설계 내압을 갖도록 설계되었다. 본 연구에서는 PHWR 원자로건물을 3차원 유한요소모델로 이상화하였으며, 구조적 파괴를 예측하기 위해 재료의 비선형성을 고려하였다. 본 논문은 고압 상태에서 격납구조물의 구조적 파괴 모드를 제시하고, 이에 대한 해석 결과를 요약하여 보여준다.

키워드
PHWR 원자로건물
부착식 텐던 시스템
구조적 파괴 형태
해석 결과
References
1

Bhabha Atomic Research Center (2007) BARC Containment Model Round Robin Analysis – Release of Model Documents. Mumbai: Bhabha Atomic Research Centre.

2

European Committee for Standardization (2004) Eurocode 2 (EC2): Design of Concrete Structures – Part 1-1: General Rules and Rules for Buildings. Brussels: CEN. EN 1992-1-1.

3

Moon, I. and Sim, J. (2004) An Ultimate Pressure Capacity Assessment of Prestressed Concrete Containment Vessel Considering Non-symmetric Factors. Journal of the Korean Society of Civil Engineers 24(3A), 639-646. (In Korean)

4

SIMULIA (2023) Abaqus Analysis User's Manual. Providence, RI: Dassault Systèmes Simulia Corp.

5

U.S. Nuclear Regulatory Commission (2010) Regulatory Guide 1.216: Containment Structural Integrity Evaluation for Internal Pressure Loadings above Design-Basis Pressure. Washington, D.C.: U.S. Nuclear Regulatory Commission. Rev. 0.

6

U.S. Nuclear Regulatory Commission (2013) Standard Review Plan 3.8.1: Concrete Containment. Washington, D.C.: U.S. Nuclear Regulatory Commission. NUREG-0800, Rev. 4.

Information
  • Publisher :Korean Institute of Bridge and Structural Engineers
  • Publisher(Ko) :한국교량및구조공학회
  • Journal Title :Journal of Structure Research and Practice
  • Journal Title(Ko) :한국교량및구조공학회 논문집
  • Volume : 4
  • No :1
  • Pages :35-45
  • Received Date : 2026-06-24
  • Revised Date : 2026-07-07
  • Accepted Date : 2026-07-09
  • DOI :https://doi.org/10.22725/JSRP.2026.4.1.35
Journal Informaiton Journal of Structure Research and Practice Journal of Structure Research and Practice
Online Submission & Review System
  • KOFST
  • KISTI Current Status
  • KISTI Cited-by
  • KCI 문헌 유사도 검사
  • orcid
  • open access
  • ccl
Journal Informaiton Journal Informaiton - close