Possibility of a Pressurized Water Reactor Concept with Highly Inherent Heat Removal Following Capability.

• ARAYA Fumimasa

  Japan Atomic Energy Research Institute

• MURAO Yoshio

  Japan Atomic Energy Research Institute

抄録

If the core power inherently follows change in heat removal rate from the primary coolant system within small thermal expansion of the coolant which can be absorbed in a practical size of pressurizer, reactor systems may have more safety and load following capability. In order to know possibility and necessary conditions of a concept on reactor core and primary coolant system of a pressurized water reactor (PWR) with such"highly inherent heat removal following capability", transient analyses on an ordinary two-loop PWR have been performed for a transient due to 50% change in heat removal with the RETRAN-02 code.<BR>The posibility of a PWR concept with the highly inherent heat removal following capability has been demonstrated under the conditions of the absolute value of ratio of the coolant density reactivity coefficient to the Doppler reactivity coefficient more than 10×10³kg•cm³ which is two to three times larger than that at beginning of cycle (BOC) in an ordinary PWR and realized by elimination of the chemical shim, the 12% lower average linear heat generation rate of 17.9 kW/m, and the 1.5 times larger pressurizer volume than those of the ordinary PWR.

収録刊行物

• Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌）

  Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌） 32 (4), 339-350, 1995

  一般社団法人 日本原子力学会

キーワード

• highly inherent heat removal following capability
• PWR type reactors
• passive safety reactor
• transient analyses
• power density
• heat removal
• RETRAN-02 code
• reactivities
• pressurizer volume

詳細情報

• CRID: 1390001204095538688
• NII論文ID: 10002072412
• NII書誌ID: AA00703720
• DOI: 10.3327/jnst.32.339
• COI: 1:CAS:528:DyaK2MXltFakur0%3D
• ISSN: 18811248
• ISSN: 00223131
• 本文言語コード: en
• データソース種別:
  • JaLC
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可