Burn-up credit in criticality safety of PWR spent fuel

被引:3
|
作者
Mahmoud, Rowayda F. [1 ]
Shaat, Mohamed K. [2 ]
Nagy, M. E. [3 ]
Agamy, S. A. [3 ]
Abdelrahman, Adel A. [1 ]
机构
[1] Atom Energy Author, Nucl Res Ctr, Dept Met, Cairo, Egypt
[2] Atom Energy Author, Nucl Res Ctr, Reactors Dept, Cairo, Egypt
[3] Univ Alexandria, Nucl & Radiat Dept, Cairo, Egypt
关键词
Compendex;
D O I
10.1016/j.nucengdes.2014.09.001
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The criticality safety calculations were performed for a proposed design of a wet spent fuel storage pool. This pool will be used for the storage of spent fuel discharged from a typical pressurized water reactor (PWR). The mathematical model based on the international validated codes, WIMS-5 and MCNP-5 were used for calculating the effective multiplication factor, k(eff), for the spent fuel stored in the pool. The data library for the multi-group neutron microscopic cross-sections was used for the cell calculations. The keff was calculated for several changes in water density, water level, assembly pitch and burn-up with different initial fuel enrichment and new types and amounts of fixed absorbers. Also, k(eff) was calculated for the conservative fresh fuel case. The results of the calculations confirmed that the effective multiplication factor for the spent fuel storage is sub-critical for all normal and abnormal states. The future strategy for the burn-up credit recommends increasing the fuel burn-up to a value >60.0 GWD/MTU, which requires new fuel composition and new fuel cladding material with the assessment of the effects of negative reactivity build up. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:628 / 633
页数:6
相关论文
共 50 条
  • [21] A study of burnup credit in criticality safety analysis for PBR spent fuel pebbles
    Wu, Shang-Chien
    Chao, Der-Sheng
    Liang, Jenq-Horng
    ANNALS OF NUCLEAR ENERGY, 2019, 132 : 347 - 356
  • [22] BURNUP CREDIT IN THE CRITICALITY SAFETY ANALYSIS OF SPENT FUEL IN TRANSPORTATION AND STORAGE SYSTEMS
    Soloviov, Vladyslav
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 6, 2014,
  • [23] TRIGA criticality experiment for testing burn-up calculations
    Persic, A
    Ravnik, M
    Zagar, T
    RRFM'99: 3RD INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT, 1999, : 187 - 191
  • [24] BURN-UP MEASUREMENTS ON REACTOR FUEL
    TRENGERE.JK
    PHYSICA NORVEGICA, 1967, 2 (04): : 313 - &
  • [25] Influence of simultaneous variations in operating parameters on burnup credit criticality analysis for PWR spent fuel assemblies
    Wu, Shang-Chien
    Chao, Der-Sheng
    Liang, Jenq-Horng
    NUCLEAR ENGINEERING AND DESIGN, 2018, 340 : 193 - 200
  • [26] Measurement of spent nuclear fuel burn-up using a new H(n,γ) method
    Nauchi, Yasushi
    Sato, Shunsuke
    Hayakawa, Takehito
    Kimura, Yasuhiko
    Suyama, Kenya
    Kashima, Takao
    Futakami, Kazuhiro
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2023, 1050
  • [27] Characteristics of a geological disposal system for the increasing burn-up of spent nuclear fuel in Korea
    Cho, Dong-Keun
    Lee, Yang
    Lee, Jong-Youl
    Choi, Jongwon
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2007, 44 (10) : 1306 - 1316
  • [28] Burn-up characteristics of ADS system utilizing the fuel composition from MOX PWRs spent fuel
    Marsodi
    Lasman, A.S.
    Nishihara, K.
    Osugi, T.
    Tsujimoto, K.
    Marsongkohadi
    Su'ud, Z.
    2002, Elsevier Ltd (29)
  • [29] Burn-up characteristics of ADS system utilizing the fuel composition from MOX PWRs spent fuel
    Marsodi
    Lasman, AS
    Nishihara, K
    Osugi, T
    Tsujimoto, K
    Marsongkohadi
    Su'ud, Z
    ANNALS OF NUCLEAR ENERGY, 2002, 29 (18) : 2173 - 2186
  • [30] Change of fuel-to-cladding gap width with burn-up in FBR MOX fuel irradiated to high burn-up
    Maeda, K
    Asaga, T
    JOURNAL OF NUCLEAR MATERIALS, 2004, 327 (01) : 1 - 10