Delayed Neutron Detection with graphite moderator for clad failure detection in Sodium-Cooled Fast Reactors

被引：13

作者：

Rohee, E. ^{[1
]}

Coulon, R. ^{[1
]}

Jammes, C. ^{[2
]}

Filliatre, P. ^{[2
]}

Normand, S. ^{[1
]}

Carrel, F. ^{[1
]}

Laine, F. ^{[1
]}

Hamrita, H. ^{[1
]}

机构：

[1] CEA, LIST, Lab Capteurs & Architectures Elect, F-91191 Gif Sur Yvette, France

[2] CEA, DEN, SPEx, LDCI,Ctr Cadarache, F-13109 St Paul Les Durance, France

来源：

ANNALS OF NUCLEAR ENERGY | 2016年 / 92卷

关键词：

Fast reactor; Sodium; Clad failure; Fission products; Neutron detection; Photoneutron noise;

D O I：

10.1016/j.anucene.2016.02.003

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：

In order to meet clean core challenges in Sodium-Cooled Fast Reactors (SFR), specific attention is paid to the cladding integrity. To monitor this integrity, Delayed Neutron Detection (DND) systems are implemented. During clad failures, neutron precursor fission products (mainly halogens: I-137, Br-87, Br-88) escape into the primary coolant. The detection of these precursors through their delayed neutron emission ensures a diagnosis on clad failures events. In DND systems, He-3 proportional counters are selected as the best available technology for neutron detection purposes. Associated with He-3 counters, polyethylene blankets are required in order to thermalize neutrons. The first part of this study is dedicated to the optimization of the DND device by Monte-Carlo simulations in order to improve the detection capability. This optimization focuses on the device design presenting a graphite based alternative to polyethylene blankets in order to remove photoneutron noise from D-2(gamma,n) reactions in polyethylene in presence of a high Na-24 activity (emission of gamma rays at 2.75 MeV). The experimental part of this study is devoted to the validation of a measuring station including an He-3 counter with carbon for neutron moderation. Both Monte-Carlo simulations and experimental results highlight the potential for a low-noise DND system based on graphite moderation. (C) 2016 Elsevier Ltd. All rights reserved.

引用

页码：440 / 446

页数：7

共 50 条

[41] Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors
Ehster, S.
Ammirabile, L.
Bubelis, E.
Carluec, B.
Droin, J. B.
Girardi, E.
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2022, 8 (01):
[42] Development of cladding materials for sodium-cooled fast reactors in India
Baldev Raj
Divakar Ramachandran
M. Vijayalakshmi
Transactions of the Indian Institute of Metals, 2009, 62 : 89 - 94
[43] EVOLUTION OF FUEL DESIGNS FOR SODIUM-COOLED FAST-REACTORS
BISHOP, JFW
HOLMES, JAG
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 20 (APR21): : 311 - 312
[44] New Concept for Sodium-Cooled Fast Breeder Reactors.
Ziegler, A.
Brennstoff-Waerme-Kraft, 1983, 35 (1-2): : 50 - 55
[45] FEATURES OF SECOND-GENERATION SODIUM-COOLED FAST REACTORS
AMOROSI, A
PETERS, NT
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1966, 9 (01): : 215 - &
[46] SOME ASPECTS OF FUEL-PIN FAILURE PROPAGATION IN SODIUM-COOLED FAST-REACTORS
FAUSKE, HK
NUCLEAR SCIENCE AND ENGINEERING, 1974, 54 (01) : 10 - 17
[47] TAGGING-GAS FAILED FUEL DETECTION AND LOCATION SYSTEM FOR SODIUM-COOLED REACTORS
Aizawa, Kosuke
Chikazawa, Yoshitaka
NUCLEAR TECHNOLOGY, 2015, 189 (02) : 143 - 151
[48] Ferritic steels for sodium-cooled fast reactors: Design principles and challenges
Baldev Raj
M. Vijayalakshmi
JOM, 2010, 62 : 75 - 83
[49] FUEL FOR ADVANCED SODIUM-COOLED FAST REACTORS: CURRENT STATUS AND PLANS
Poplavskii, V. M.
Zabudko, L. M.
Shkabura, I. A.
Skupov, M. V.
Bychkov, A. V.
Kislyi, V. A.
Kryukov, F. N.
Vasiliev, B. A.
ATOMIC ENERGY, 2010, 108 (04) : 267 - 273
[50] SAFETY ASSESSMENT OF FAST SODIUM-COOLED REACTORS IN UNITED-KINGDOM
FARMER, FR
NUCLEAR SAFETY, 1970, 11 (04): : 283 - &

← 1 2 3 4 5 →