Design of Neutron Flux Monitoring System for Sodium Cooled Fast Reactors

被引：0

作者：

Nagaraj, C. P. ^{[1
]}

Sivaramakrishna, M. ^{[1
]}

Madhusoodanan, K. ^{[2
]}

Chellapandi, P. ^{[3
]}

机构：

[1] IGCAR, PPG RDG, NIS ICD, Kalpakkam, Tamil Nadu, India

[2] PPG RDG, IGCAR, Kalpakkam, Tamil Nadu, India

[3] RDG, IGCAR, Kalpakkam, Tamil Nadu, India

来源：

2013 3RD INTERNATIONAL CONFERENCE ON ADVANCEMENTS IN NUCLEAR INSTRUMENTATION, MEASUREMENT METHODS AND THEIR APPLICATIONS (ANIMMA) | 2013年

关键词：

neutron flux; PFBR; high temperature fission chamber; pulse mode; Campbell mode;

D O I：

暂无

中图分类号：

TM [电工技术]; TN [电子技术、通信技术];

学科分类号：

0808 ; 0809 ;

摘要：

Neutron Flux Monitoring System (NFMS) plays an important role in the safety of sodium cooled fast reactors. NFMS measures the reactor power and the reactivity changes in the core. The neutron detectors sense the neutron flux at suitable locations representing the core flux and the signal conditioning electronics processes the signal to get logarithmic power, linear power, period and reactivity parameters. These parameters aid in control of reactor power and initiate safety action on crossing the threshold.

引用

页数：7

共 50 条

[41] TECHNICAL DEVELOPMENT IN GERMANY OF SODIUM COOLED FAST BREEDER REACTORS
不详
BRENNSTOFF-WARME-KRAFT, 1968, 20 (06): : 265 - &
[42] Fuels for sodium-cooled fast reactors: US perspective
Crawford, Douglas C.
Porter, Douglas L.
Hayes, Steven L.
JOURNAL OF NUCLEAR MATERIALS, 2007, 371 (1-3) : 202 - 231
[43] INCIPIENT BOILING DETECTION IN SODIUM-COOLED FAST REACTORS
BONNET, JA
OSBORN, RK
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (01): : 309 - &
[44] SUCCESSIVE DEVELOPMENT PHASES FOR SODIUM-COOLED FAST REACTORS
Bagdasarov, Yu. E.
Kamaev, A. A.
ATOMIC ENERGY, 2012, 111 (06) : 389 - 397
[45] Some thermal hydraulic challenges in sodium cooled fast reactors
Tenchine, D.
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (05) : 1195 - 1217
[46] THERMAL HYDRAULICS OF SODIUM-COOLED FAST REACTORS: KEY DESIGN AND SAFETY ISSUES AND HIGHLIGHTS
Ninokata, Hisashi
Kamide, Hideki
NUCLEAR TECHNOLOGY, 2013, 181 (01) : 11 - 23
[47] Under-Sodium Viewing Techniques in Sodium-Cooled Fast Reactors
Joo, Young-Sang
JOURNAL OF THE KOREAN SOCIETY FOR NONDESTRUCTIVE TESTING, 2012, 32 (04) : 439 - 447
[48] Towards the Characterization of the Bubble Presence in Liquid Sodium of Sodium Cooled Fast Reactors
Cavaro, M.
Payan, C.
Jeannot, J. P.
2013 3RD INTERNATIONAL CONFERENCE ON ADVANCEMENTS IN NUCLEAR INSTRUMENTATION, MEASUREMENT METHODS AND THEIR APPLICATIONS (ANIMMA), 2013,
[49] Measurement of the Total and Fast Neutron Flux in the Compact Sodium-Cooled Reactor KNK-1.
Reichel, H.
Ruppert, E.
1600, (31):
[50] How could fuel corrosion influence the delayed neutron signal time evolution in sodium cooled fast reactors
Ding, C.
Filliatre, P.
Desgranges, L.
Friant, D.
NUCLEAR ENGINEERING AND DESIGN, 2022, 398

← 1 2 3 4 5 →