이중냉각 핵연료 상단고정체의 기계적 성능평가

국문 초록 (Abstract)

핵연료집합체는 상단고정체, 하단고정체, 지지격자체, 제어관/계측관과 핵연료봉의 5 가지 주요 구성품으로 이루어져 있다. 여기서 상/하단고정체는 다른 구성품과 달리 ASME, Section III, Division 1 ? Subsection NB 의 운전조건 A, B 에서의 stress intensity limits 를 만족하여야 한다. 이중냉각 핵연료집합체는 집합체당 출력을 증가시키기 위해서 기존의 가압경수로용 핵연료집합체에서 핵연료봉의 배열과 위치를 변화시켰는데 이로 인하여 핵연료봉 내/외부유로로 냉각수가 잘 흐를 수 있도록 상/하단고정체의 유로판의 형상을 수정하여야 한다. 본 논문에서는 설계하중조건에 대하여 수정된 상단고정체 유로판의 건전성평가를 위해 수행한 응력선형화과정을 자세히 설명하고 평가결과에 대하여 기술하였다.

다국어 초록 (Multilingual Abstract)

A fuel assembly consists of five major components, i.e., a top end piece (TEP), a bottom end piece (BEP), spacer grids (SGs), guide tubes (GTs) and an instrumentation tube (IT); in addition, it also includes fuel rods (FRs). The TEP/BEP should satisfy stress intensity limits according to the conditions A and B of ASME, Section III, Division 1?Subsection NB. In a dual-cooled fuel assembly, the array and position of fuel rods are different from those in a conventional PWR fuel assembly; these changes are necessary for achieving power uprating. The flow plates of the TEP and BEP have to be modified accordingly. The pattern and shape of the flow holes were newly designed. To verify the strength compatibility, the Tresca stress limit according to the ASME code was investigated in the case of an axial load of 22.241 kN. In this paper, the stress linearization procedure for strength evaluation of a newly designed TEP is presented.

목차 (Table of Contents)

• 초록
• Abstract
• 1. 서론
• 2. 이중냉각 핵연료 상단고정체 유로판
• 3. 응력선형화(stress linearization)
• 4. 구조해석모델
• 5. 건전성평가를 위한 응력선형화
• 6. 결론
• 후기
• 참고문헌

참고문헌 (Reference)

1 Hollinger, G, "Three Dimensional Stress Criteria-Summary PVRC Project" 122 : 2000

2 European Commission Joint Research Center, "The Design by Analysis Manual"

3 Kim, H.-K, "Technical Challengers for Dual-Cooling Fuel Structural Components" 2007

4 Choi, W.-S, "Shape Optimization of Perforated Reactor Head Considering a Stress Linearization" 4 : 22-29, 2008

5 "Mathmatica v3.0 online documentation"

6 "KAERI/TR-2289, Shape Optimization of the SMART Central Cover by the ASME Code Criteria"

7 "KAERI/RR-3088, Development of Design Technology for Dual-Cooled Fuel Structure"

8 Hibbitt, H.D, "ABAQUS user's Manual (ver 6.8-1)" HKS Inc 2008

9 Hechmer, J.L, "3D Stress Criteria Guidelines for Application" WRC Bulletin 429-, 1998

10 The American Society of Mechanical Engineers, "2007 ASME Boiler & Pressure Vessel Code, Section III, Division 1, Subsection NB, Class 1 Components Rules for Construction of Nuclear Facility Components"

11 The American Society of Mechanical Engineers, "2007 ASME Boiler & Pressure Vessel Code, Section II, Part D, Properties (Customary) Materials"