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論文

Influence of initial conditions on rod behaviour during boiling crisis phase following a reactivity initiated accident

Georgenthum, V.*; 杉山 智之

Proceedings of OECD/NEA Workshop on Nuclear Fuel Behaviour during Reactivity Initiated Accidents (CD-ROM), 9 Pages, 2009/09

In the frame of their research programs on high burnup fuel safety, the IRSN and JAEA performed a large set of tests devoted to the study of PWR fuel rod behaviour during Reactivity Initiated Accident (RIA) respectively in the CABRI and NSRR. The test conditions are different in terms of coolant nature, temperature and pressure. In the CABRI reactor, tests were performed so far with sodium coolant at 280 $$^{circ}$$C and 3 bar. In the NSRR most of the tests were performed with stagnant water at 20 $$^{circ}$$C and atmospheric pressure, but recently a new high temperature high pressure capsule has been developed which allows up to 280 $$^{circ}$$C and 70 bar. This paper discusses the influence of test conditions on rod behaviour during boiling phase, based on test results and SCANAIR code calculations. The study shows that when the boiling crisis is reached, the initial inner and outer rod pressure have an essential impact on the clad strain and possible ballooning.

論文

Status of fission gas dynamics programme

Georgenthum, V.*; 杉山 智之

DPAM-SEMCA-2008-330, 36 Pages, 2009/05

原子力機構と仏Institut de Radioprotection et de S$^u$ret$'e$ Nucl$'e$aire(IRSN)では、反応度事故時のペレットからの気体核分裂生成物(FPガス)放出に関する動的挙動解明を目的とした試験を共同で計画している。このFGD(Fission Gas Dynamics)試験では、高燃焼度燃料に対してNSRRでパルス照射を行い、FPガス放出の動的挙動及びFPガスが被覆管に対して及ぼす機械的負荷の大きさを評価する。本報告では、FGD試験の目的、試験準備状況、検討課題及び高燃焼度燃料を用いた試験の予備解析結果を示す。

論文

Fracture mechanics approach for failure mode analysis in CABRI and NSRR RIA tests

Georgenthum, V.*; 杉山 智之; 宇田川 豊; 更田 豊志; Desquines, J.*

Proceedings of Water Reactor Fuel Performance Meeting 2008 (WRFPM 2008) (CD-ROM), 8 Pages, 2008/10

An analysis based on an Elastic Plastic Fracture Mechanics approach has been derived to understand the cladding failure conditions during the Pellet Cladding Mechanical Interaction phase of an RIA transient. The impact of incipient cracks at the cladding periphery has been evaluated through the calculation of J-integral. The J-integral is evaluated in a module coupled with the SCANAIR code and compared to the critical value of the J-integral deduced from the fracture toughness of Zircaloy. The clad metallography on CABRI and NSRR tested fuel rods provided the depth of brittle zone, i.e., the length of incipient crack. This analysis shows the J-integral can be used both in the elastic and elasto-plastic ranges to predict the failure occurrences. The study also points out that due to the strong dependence of hydride solubility with temperature, the conditions are more severe in the NSRR room temperature than in the CABRI or the Pressurized Water Reactor temperature.

論文

A Comparative analysis of CABRI CIP0-1 and NSRR VA-2 reactivity initiated accident tests

Petit, M.*; Georgenthum, V.*; 杉山 智之; Quecedo, M.*; Desquines, J.*

Proceedings of EUROSAFE Forum 2007 (Internet), 9 Pages, 2007/11

Zirlo is an improved fuel cladding material that was developed to accommodate constraints associated with increasing burnups in a more severe duty operation. The behavior of Zirlo irradiated above 75 GWd/t under RIA conditions was studied in CABRI CIP0-1 and NSRR VA-2 tests. The samples were initially similar but VA-2 failed at relatively low enthalpy whereas CIP0-1 did not fail. Because test conditions were different in terms of initial temperature, coolant nature and power pulse width, it is necessary to use a transient fuel code to compare the two results. Using SCANAIR and CLARIS it was shown that the concentration of hydrogen precipitates at the temperature of the test is of primary importance to assess both experiments in a consistent manner. The analysis demonstrated that room temperature is a testing condition much more severe than that expected at typical PWR conditions.

口頭

Analysis of CIP0-1 and VA-2 tests

Georgenthum, V.*

no journal, , 

同一仕様のZirlo被覆UO$$_{2}$$燃料棒を対象とした反応度事故(RIA)模擬実験VA-2及びCIP0-1をそれぞれNSRR及び仏CABRI炉において実施した。両燃料棒はスペイン・バンデロスPWRにおいて燃焼度約80GWd/tまで照射され、被覆管の表面酸化膜厚さは約80$$mu$$m、水素吸収量は約1000ppmに達していた。燃料棒は、VA-2実験では燃料エンタルピ55cal/gにおいて破損したが、CIP0-1実験では92cal/gの燃料エンタルピに対しても破損しなかった。照射後試験によれば、VA-2燃料棒では被覆管肉厚の外側半分の領域で水素化物析出による脆化が見られたのに対し、CIP0-1燃料棒では被覆管外周部の水素化物リム(厚さ50$$mu$$m)においてのみ脆化が観察された。両者の違いは実験中の被覆管温度の違いで説明できる。SCANAIRコードによる解析によればCIP0-1では被覆管外面温度が約400$$^{circ}$$Cに達しており、水素化物が再固溶したと予想される。一方、VA-2では被覆管温度が低いままだったため再固溶が起こらず、脆性が高かったと解釈される。

口頭

The Fission gas dynamics program

Tr$'e$gour$'e$s, N.*; Georgenthum, V.*; 杉山 智之

no journal, , 

An experimental program to investigate dynamics of fission gas release during a reactivity initiated accident is being carried out as a joint project of JAEA and IRSN, France. The objectives, methodology and current status are presented as well as the preliminary test results related with sensor development.

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